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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 />

Safety objectives require that nuclear <strong>in</strong>stallations are designed and operated so as to keep<br />

all sources of radiation exposure under strict technical and adm<strong>in</strong>istrative control.<br />

However, the radiation protection objective does not preclude limited exposure of people<br />

or the release of legally authorized quantities of radioactive materials to the environment<br />

from <strong>in</strong>stallations <strong>in</strong> operational states. Such exposures and releases, however, must be<br />

strictly controlled and must be <strong>in</strong> compliance with operational limits and radiation<br />

protection standards.<br />

In order to achieve these three safety objectives, <strong>in</strong> design<strong>in</strong>g a nuclear power plant, a<br />

comprehensive safety analysis is carried out to identify all sources of exposure and to<br />

evaluate radiation doses that could be received by workers at the <strong>in</strong>stallation and the<br />

public, as well as potential effects on the environment. The safety analysis exam<strong>in</strong>es: (1)<br />

all planned normal operational modes of the plant; (2) plant performance <strong>in</strong> anticipated<br />

operational occurrences; (3) design basis accidents; and (4) event sequences that may<br />

lead to a severe accident. On the basis of this analysis, the robustness of the eng<strong>in</strong>eer<strong>in</strong>g<br />

design <strong>in</strong> withstand<strong>in</strong>g postulated <strong>in</strong>itiat<strong>in</strong>g events and accidents can be established, the<br />

effectiveness of the safety systems and safety related items or systems can be<br />

demonstrated, and requirements for emergency response can be established.<br />

Although measures are taken to control radiation exposure <strong>in</strong> all operational states to<br />

levels as low as reasonably achievable (ALARA) and to m<strong>in</strong>imize the likelihood of an<br />

accident that could lead to the loss of normal control of the source of radiation, there is a<br />

residual probability that an accident may happen. Measures are therefore taken to ensure<br />

that the radiological consequences are mitigated. Such measures <strong>in</strong>clude: eng<strong>in</strong>eered<br />

safety features; on‐site accident management procedures established by the operat<strong>in</strong>g<br />

organization; and possibly off‐site <strong>in</strong>tervention measures established by appropriate<br />

authorities <strong>in</strong> order to mitigate radiation exposure if an accident has occurred.<br />

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