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NUREG-1537, Part 2 - NRC

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CHAPTERS<br />

Ewauation 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 design bases, functional descriptions, and procedures for the primary<br />

coolant makeup water system give reasonable assurance that the quantity<br />

and quality of water required will be provided.<br />

* The system design or procedures will prevent overfilling of the primary<br />

coolant system or malfimetion of the makeup water system and will prevent<br />

the loss or release of contaminated primary coolant that would exceed the<br />

requirements of 10 CFR <strong>Part</strong> 20 and the facility ALARA program<br />

guidelines.<br />

* The system design or procedures will prevent contaminated primary<br />

coolant from entering the potable water system through the makeup water<br />

systemn<br />

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

reasonable assurance of necessary makeup water system operability for<br />

normal reactor operations.<br />

5.6 Nitrogen-16 Control System<br />

Areas of ReWiew<br />

Non-power reactors that use either light or heavy water for neutron moderation or<br />

cooling will produce nitrogen-16 by the fast neutron-proton reaction in oxygen-16.<br />

Nitrogen-16, a high-energy beta and gamma ray emitter with a half-life of<br />

approximately 7 seconds, is a potential source of high radiation exposure at watercooled<br />

non-power reactors. It tends to remain dissolved in the primary coolant<br />

water as it leaves the core. The quantity and concentration of nitrogen-16 should<br />

be considered and pro'visions made to control personnel exposure. Because of the<br />

retively short half-life potential doses can be decreased by delaying the coolant<br />

within shielded regions. For reactors using natural-convection cooling in a large<br />

open pool, stirring or diffusing the convection flow to the surface can produce a<br />

delay.'' For forced-flow cooling, passing the coolant through a large shielded and<br />

baffled tank can produce the delay. In some non-power reactor designs, the entire<br />

primary coolant system may be shielded. Specific areas of review for this section<br />

are discussed in Section 5.6 of the format and content guide.<br />

<strong>NUREG</strong>-<strong>1537</strong>, PART 2 5-14 REV. 0,2/96<br />

<strong>NUREG</strong>-lS37, PART 2 5-14 REVt. O. 2Vg6

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