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Regional Basic Professional Training Course in Korea

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<strong>Regional</strong> <strong>Basic</strong> <strong>Professional</strong> <strong>Tra<strong>in</strong><strong>in</strong>g</strong> <strong>Course</strong> (BPTC) on Nuclear Safety<br />

<strong>in</strong>formation. For example, the limits on process variables of the core, heat transport<br />

systems, and energy conversion systems should be stated <strong>in</strong> terms of <strong>in</strong>strument read<strong>in</strong>gs<br />

available <strong>in</strong> the control room. In modern practice, safety parameter display systems are<br />

provided <strong>in</strong> many plants to help the operators perceive and understand the plant’s safety<br />

status.<br />

10.2.1. Introduction<br />

10.2. SAFETY SYSTEM SETTINGS<br />

This chapter considers the basic prelim<strong>in</strong>ary concepts for def<strong>in</strong><strong>in</strong>g the design of reactor<br />

safety system. Reactor safety systems are designed to protect the plant <strong>in</strong> case of<br />

predeterm<strong>in</strong>ed accident scenarios. These scenarios are grouped <strong>in</strong>to categories accord<strong>in</strong>g<br />

to an <strong>in</strong>creas<strong>in</strong>g probability of occurrence:.<br />

Category 1 correspond<strong>in</strong>g to the area of normal operation of the plant;<br />

Category 2 corresponds to <strong>in</strong>cidents whose occurrence frequency is estimated to be<br />

between 1 and 10‐2 times per year, per reactor;<br />

Category 3, between 10 ‐2 and 10 ‐4 times per year, per reactor;<br />

Category 4, between 10 ‐4 and 10 ‐6 times per year, per reactor.<br />

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