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NUREG-1537, Part 2 - NRC

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APPDIX 1 8.1<br />

mechanical failure or degradation related to neutron irradiation, corrosion, and<br />

erosion. Additionally, modifications to the biological shield or to reactor operating<br />

characteristics will be acceptable (1) if they do not decrease physical integrity of<br />

the shield against crackdng or other structural malfunctions due design loads (eg.,<br />

natural or reactor-induced forces) or neutron irradiation and (2) if the protection of<br />

the radiation shielding does not decrease below acceptable requirements as<br />

analyzed in Chapter 11 of the staffs safety evaluation report.<br />

Review Procedures<br />

The reviewer should compare design changes against the as-built systems to<br />

confirm how proposed changes will affect the structural integrity, resistance to<br />

failure or degradation, or radiation protection factors of the pool and biological<br />

shield for normal operations or postulated accident conditions.<br />

Evluation Findings<br />

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

following types of conclusions, which will be included in the staff's safety<br />

evaluation report:<br />

* Any proposed chafiges to the poof or to the biological shield for the<br />

conversion are required to accommodate the'conversion.<br />

* Proposed modifications to the pool, shield, or reactor operating conditions<br />

will not significantly decrease resistance to failure, or cause new or<br />

accelerated degradation or loss of integrity.<br />

* Any new conversion-related pool or shield safety issues are addressed by<br />

proposed modifications to the pool and shield systems.<br />

* (If no chages to the pool or biological shield are proposed) The<br />

information submitted supports the conclusion that the existing systems<br />

will provide comparable protection to the public with the LEU fuel.<br />

4.4 Core Support Structure<br />

Areas of Review<br />

The reviewer should evaluate the design features, construction materials, criteria<br />

for rigidity and weight support, and capability to maintain fuel and other core<br />

components in acceptable positions. The reviewer should also compare the weight<br />

and other relevant stresses imposed by the existing HEU core components to those<br />

of the proposed LEU core components.<br />

<strong>NUREG</strong>-<strong>1537</strong>, PMT2 12 REV. 0,2/96<br />

<strong>NUREG</strong>-<strong>1537</strong>; PART2 12 REV. 0, 2/96<br />

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