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NUREG-1537, Part 2 - NRC

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CHAPTER I<br />

the applicant discussed in the SAR how the normal operating use and malfunctions<br />

of the licensed facility could affect the other facilities. The reviewer should also<br />

assess the discussion in the SAR of the effect of the shared facilities on the safety<br />

of the subject facility. The reviewer may need to review discussions and analyses<br />

in other sections of the SAR.<br />

Evaluation Findings<br />

This section of the SAR should contain sufficient information to support the<br />

following types of conclusions, considering that most of the conclusions in this<br />

section summarize the analysis and findings of other parts of the staffss safety<br />

evaluation report:<br />

* The shared facilities are clearly and completely listed and the other users<br />

are identified. The applicant has shown that a malfunction or a loss of<br />

function of these shared facilities would not affect the operation of the nonpower<br />

reactor, nor would it damage the non-power reactor or its capability<br />

to be safely shut down.<br />

* Either normal operation or a loss of function of the shared facilities would<br />

not lead to uncontrolled release of radioactive material from the licensed<br />

facility to unrestricted areas, or in the event of release, the exposures are<br />

analyzed in Chapter 13, "Accident Analyses," and are found to be<br />

acceptable.<br />

1.5 Comparison With Similar Facilities<br />

Areas of Review<br />

Since the early 1940s, several hundred non-power reactors have been built in the<br />

United States, and many more were built in other countries. The first few such<br />

reactors established the safety considerations and principles for the non-power<br />

reactors that followed.<br />

Several non-power reactors not licensed by <strong>NRC</strong> were used as early prototypes or<br />

to develop fuels or other components. Examples of prototype or developmental<br />

test facilities, whose results were adopted by licensed facilities, include the<br />

following:<br />

* bulk shielding facility (B SF)<br />

* materials testing reactor (MTR)<br />

* special power excursion reactor test (SPERT)<br />

* Chicago Pile #5 or Argonne research reactor (CP-5)<br />

<strong>NUREG</strong>-<strong>1537</strong>,PART2 1-8 REV 0,2/96<br />

<strong>NUREG</strong>- 1 537, PART 2 1-8 REV 0, 2/96

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