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NUREG-1537, Part 2 - NRC

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CHAPTER5<br />

analyzed. The reviewer should verify that the potential personnel radiation<br />

exposures from sources shielded by primary coolant have been analyzed and the<br />

protection factors provided by the coolant have been discussed.<br />

Evaluation 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 staffs safety<br />

evaluation report:<br />

The applicant has described and analyzed auxiliary systems that use primary<br />

coolant for functions other than in-core fuel cooling, has derived the design<br />

bases from other chapters of the SAR, has analyzed any reactor<br />

components located in high radiation areas near the core for potential<br />

heating that could cause damage to the reactor core or failure of the<br />

component, and has planned acceptable methods to remove sufficient heat<br />

to ensure the integrity of the components The coolant for these systems is<br />

obtained from the purified prinmary coolant system without decreasing the<br />

capability of the system below its acceptable performance criteria for core<br />

cooling<br />

* The applicant has analyzed any reactor components or auxiliary systems for<br />

which primary coolant helps shield personnel from excessive radiation<br />

exposures. The use of the coolant for these purposes is acceptable, and the<br />

estimated protection factors limit the exposures to the requirements of<br />

10 CFR <strong>Part</strong> 20 and the facility ALARA program guidelines. There is<br />

reasonable assurance that credible and postulated malfunctions of the<br />

auxiliary cooling systems will not lead to uncontrolled loss of primary<br />

coolant, radiation exposures, or release of radioactivity to the unrestricted<br />

environment that exceeds the requirements of 10 CFR <strong>Part</strong> 20 and the<br />

facility ALARA program guidelines.<br />

* The technical specifications, including testing and surveillance, provide<br />

reasonable assurance of necessary auxiliary cooling system operability for<br />

normal reactor operations.<br />

5.8 Reference<br />

Griess, J. C., et al., ORNL-3541, "Effect of Heat Flux on the Corrosion of<br />

Aluminum by Water," <strong>Part</strong> IV, Oak Ridge National Laboratory, February 1964.<br />

<strong>NUREG</strong>-<strong>1537</strong>,PNa2 5-18 REV 0,2/96<br />

I<strong>NUREG</strong>-<strong>1537</strong>,PART2 5-18 REV 0. 2/96

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