NUREG-1537, Part 2 - NRC

10 EXPERIMENTAL FACILITIES AND
UTILIZATION
10.1 Summary
HEU TO LEU CoNvERsioN
The experimental program is the principal reason for the existence of most nonpower
reactors. Because the program might be affected by the conversion of the
reactor core from HEU to LEU fuel, it and the associated experimental facilities
require review, especially the experimental facilities located within or adjacent to
the core. The reviewer should also address procedures for use of these facilities to
determine whether they require change to accommodate the conversion.
10.2 Experimental Irradiation Facilities
Areas of Review
BIEU to LEU conversion probably should not require modifications to the
experimental facilities. However, if the conversion requires changes in core size,
core shape, or relocation of control elements, or because of changes in the neutron
spectrum of the reactor, some experimental facilities could require modification
such as beam ports or pneumatic 'rabbit' systems. The areas of review should
include designs for component modifications, changes in the radiation -
characteristics or environments of an experiment facility, changes in reactivity
effects and worths of experimental facilities or the associated experiments, and
changes in procedures for the experimental facilities in the LEU-fueled reactor. If
these topics are analyzed and reviewed in detail in some other section of the safety
analysis, the reviewer should refer to those sections.
Possible damage to the reactor itself or possible overexposure of personnel to
radiation as a result of malfunction or inadequate design of an experimental facility
(or its controls) are appropriate areas of review related to BEU to LEU
conversion.
Acceptance Criteria
Acceptance criteria should be based on the following6considerations: Any changes
in the physical or functional characteristics of experiment facilities, performance of
experiments, or reactor operating characteristics required by the conversion from
HEU to LEU should be acceptable if they will not (I) lead to unanalyzed damage
to the reactor, fuel, or controls; (2) interfere with adequate reactor shutdown; (3)
degrade reactor core cooling; or (4) lead to radiation exposure from operations to
the facility staff or to the public larger than acceptable limits (e.g., 10 CFR
Rrv 0,2/96 31. STANDAP.D REVIEW PLAN
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