NUREG-1537, Part 2 - NRC

CH I
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*Any unique safety design features of the facility different from previously
licensed non-power reactor facilities should be highlighted.
Review PFindues
The reviewer should confirm that the applicant submitted all information requested
in the format and content guide.
The reviewer should confirm that the introduction contains suffiaent information
to support conclusions that the applicant and the proposed facility fall within the
scope of NRC licensing authority and that the evaluations and conclusions of other
sections of the SAR will address the relevant details of the facility.
Evaluation Findings
The NRC does not write evaluation findings for the introduction of the SAR.
Section 1.1 of the staffs safety evaluation report serves as an introduction to the
NRC report and has a standard format. Section 1 of the 'Safety Evaluation Report
Related to the Renewal of the Facility License for the Research Reactor at the
Dow Chemical Company," NUREG-1312, April 1989, an example of the standard
format, is reproduced here as Appendix 1.1. The statements should be
appropriately modified for an initial application for construction and operation. In
the introduction to the safety evaluation report, the staff identifies the applicant,
identifies the licensing action that is evaluated, lists the dates of the application and
supplements, lists the documents submitted by the applicant, provides information
on where the material is available for review by the public, states the purpose of
the review, lists the requirements and standards used in the review, and states who
performed the review for NRC.
1.2 Summary and Conclusions on Principal Safety
Considerations
Areas of Review
The reviewer should ensure that the SAR discusses all possibilities for radiological
exposure to the public that could result from operation of the facility. In this
section, the applicant should sunmarize the types of radiological exposure, the
magnitude of potential radiation exposure, and the design features that control and
limit the potential exposure to acceptable levels prescribed by regulations. These
safety considerations include the range of normal operations and accident scenarios
that influenced the location and design of the non-power reactor facility.
Areas of review should include the following:
NUREG-1537,PART2 1-2 REV 0, 2196