NUREG-1537, Part 2 - NRC

Acceptance Criteria
ExPRIMENTAL FACLriEs AND U.TAio*
The acceptance criteria for the information on the experimental facilities include
the following:
* Safety limits (SLs), limiting safety system settings (LSSSs), and LCOs for
the reactor should be derived from analyses in this and other chapters and
included in the reactor facility technical specifications. The analysis in this
section of the SAR should show that the components and the functional
design of the experimental facilities will ensure that no reactor LSSS or
LCO will be exceeded during normal operations of these experimental
facilities and that no SL will be'exceeded during accident conditions.
Consideration should include the full range of reactivity, thermal power
level, fuel temperature, pressure, and pool depth above the core.
* The physical dimensions should be such that the volume is not sufficient to
produce more of a positive reactivity insertion if suddenly voided or
flooded than that analyzed in Chapter 13 of the SAR. The experimental
facility should not skew the neutron flux distribution sufficiently to mask
safety signals or peak theineution flux or power densities beyond values
analyzed in other applicable chapters.
The thickness of the walls and the strength of the welds of the experimental
facility should preclude any deformation that would result from the
maximum postulated pressure, pulse or steady, that could damage
surrounding fuel, compromise the integrity of the experimeital facility, or
interfere with the reactor safety or control system. The applicant should
thoroughly investigate the chemical and physical properties of the
materials, including vulnerability to corrosion, erosion, and oxidation,
compatibility, and strength, for the interior and exterior environments of
the experimental ity.
* The mechanical means of securing the experimental facility should provide
-asurance that the facility cannot move inadvertently. In general, positive
fastening methods and materials; such as welds, bolts, sleeves, and collars,
are required.
* With regard to the shielding of and control of access to, experimental
-fcility areas, this section of the SAR should contain descriptions and
analysis showing that the placement,' dimensions, and materials are
' 'sfficient to limit the expected radiation dose to nperimenters, reactor
operators, and other personnel to levels that are'bilow those required by
10 CFR Part 20 and that are consistent with the facility ALARA program.
The analysis should show all pertinent radiation sources, distances,
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