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Regional Basic Professional Training Course in Korea

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the safety function<br />

would be required<br />

(e.g. RHR)<br />

3 1. Support<strong>in</strong>g of class<br />

1, 2 and 3 safety<br />

functions (no<br />

<strong>in</strong>crease <strong>in</strong> radiation<br />

exposure)<br />

2. Prevention of<br />

radiation exposure<br />

from sources outside<br />

reactor coolant<br />

system<br />

3. Reactivity control<br />

on a slower time<br />

scale than <strong>in</strong> class 1<br />

and 2<br />

4. Ma<strong>in</strong>ta<strong>in</strong><strong>in</strong>g<br />

sub‐criticality of<br />

fuel (outside reactor<br />

coolant system)<br />

5. Removal of decay<br />

heat from irradiated<br />

fuel (outside reactor<br />

coolant system)<br />

6. Safety Classification Of Structures, Systems and Components<br />

emergency core cool<strong>in</strong>g (e.g. refuel<strong>in</strong>g water storage tank).<br />

3 Equipment, not <strong>in</strong>cluded <strong>in</strong> SC‐1 or SC‐2, that is designed to<br />

accomplish the follow<strong>in</strong>g nuclear safety functions that:<br />

1. ensure hydrogen control of the primary conta<strong>in</strong>ment<br />

atmosphere to acceptable limits, except for primary<br />

conta<strong>in</strong>ment boundary extension function;<br />

2. remove radioactive material from the atmosphere of<br />

conf<strong>in</strong>ed spaces outside primary conta<strong>in</strong>ment. (e.g. control<br />

room or fuel build<strong>in</strong>g) conta<strong>in</strong><strong>in</strong>g SC‐1, SC‐2, or SC‐3<br />

equipment;<br />

3. <strong>in</strong>troduce negative reactivity to achieve or ma<strong>in</strong>ta<strong>in</strong><br />

sub‐critical reactor conditions (e.g. boron makeup);<br />

4. provide or ma<strong>in</strong>ta<strong>in</strong> sufficient reactor coolant <strong>in</strong>ventory for<br />

core cool<strong>in</strong>g (e.g. reactor coolant normal makeup system);<br />

5. ma<strong>in</strong>ta<strong>in</strong> geometry with<strong>in</strong> the reactor to ensure core<br />

reactivity control or core cool<strong>in</strong>g capability (e.g. core<br />

support structures);<br />

6. structurally load‐bear or protect SC‐l, SC‐2, or SC‐3<br />

equipment (This applies to concrete or steel structures that<br />

are not with<strong>in</strong> the scope of the KEPIC MN (nuclear<br />

mechanical) <strong>in</strong> accordance with Notice of MEST<br />

No.2008‐14, and its correspond<strong>in</strong>g code (ASME Boiler and<br />

Pressure Vessel Code Section III);<br />

7. provide radiation shield<strong>in</strong>g for the control room or off‐site<br />

personnel;<br />

8. ensure required cool<strong>in</strong>g for liquid‐cooled stored fuel (e.g.<br />

spent fuel storage pool and cool<strong>in</strong>g system);<br />

9. ensure nuclear safety functions provided by SC‐1, SC‐2, or<br />

SC‐3 equipment (e.g. provide heat removal for SC‐l, SC‐2,<br />

or SC‐3 heat exchangers, provide lubrication of SC‐2 or<br />

SC‐3 pumps, provide fuel oil to the emergency diesel<br />

❙ 383 ❙

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