NUREG-1537, Part 2 - NRC

REAcToP.DESauJTlON
similar operating characteristics Reasonable assurance exists that the
scram features designed for this reactor.will perform as necessary to ensure
fuel integrity and to protect the health and safety of the public.
(For pulsing reactors) The design and functional description of the
transient rod system offer reasonable assurance that pulses will be
reproducible and can be limited to values that maintain fuel integrity as
determined by the thennal-hydraulic analyses
* The control rod design includes reactivity worths that can control the
excess reactivity, planned for the reactor, including ensuring an acceptable
shutdown reactivity and margin, as defined and specified in the technical
specifications.
Changes in reactivity caused by control rod dynamic characteristics are
acceptable. The staff evaluations included maximum scram times and
maximum rates of insertion of positive reactivity for normal and ramp
insertions caused by system malfunctions.
* The applicant has jusified appropriate design limits, limiting conditions for
operation, and surveillance requirements for the control rods and included
them in the techidical specifications.
4.2.3 Neutron Moderator and Reflector
Areas of Review
In this section of the SAR, the applicant should describe moderators and reflectors
designed into the reactor core and their special features. The cores of most nonpower
reactors consist of metallic fuel elements immersed in moderator and
surrounded by either a liquid or solid neutron reflector. The solid reflectors are
chosen primarily for favorable nuclear properties and physical characteristics. In
some pool-type reactors (e.g., TRIGA), the fuel elements contain some of the core
neutron moderator and reflector material. Section 4.2.1 of the SAR should
contain a description of the relationship of all moderators to the core. For most
non-power reactors, the water neutron moderator and reflector also function as the
coolant, as discussed in Chapter 5. Buildup of contaminating radioactive material
in the moderator or coolant and reflector during reactor operation should be
discussed in Chapter I1, 'Radiation Protection Program and Waste Management,"
ofthe SAR..
*Aea's of review should include the following: -
* geometry
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