Abstract
This chapter addresses the operational radiological surveillance aspects of a light water reactor radiation protection (RP) program. Operational aspects include those functions associated with daily surveillance and maintenance activities in support of plant operations. Those activities typically associated with operational radiation protection functions at the working level are presented. These activities include performance of radiological surveys, radiological signposting, demarcation of radiological areas, access control, preparation of radiation work permits and job coverage activities.
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Notes
- 1.
It is not uncommon to find contamination survey results reported to three or four significant figures. Such results are of dubious value and health physicists should ensure undue significance is not applied to data unnecessarily. Based upon counting system efficiencies, smear survey area and associated parameters, smear results may be “technically “accurate. However, it should be realized that the actual survey area may have transferrable contamination levels that vary significantly from the reported results.
- 2.
Even though contamination survey results are often reported as gross beta-gamma activity, analysis equipment often used employs a GM or proportional type detector that has had its efficiency determined by use of a beta emitter calibration source. Under these circumstances and due to the low gamma sensitivity of these type detectors, the reported activity may be primarily due to the beta component of the contamination. Any moisture present will result in self-absorption of the beta particles to some degree. Consequently, if this affect is not accounted for, the measured activity may be lower than that actually present.
- 3.
Throughout this text the use of SI units have been referenced whenever possible. However, when dealing with contamination limits concerning the designation of contaminated areas, high contamination areas, and release values for equipmen and workers exiting the RCA the conventional units have been specified. These limits were based on “rounded” values that were convenient to use in-the-field and had gained widespread acceptance in the USA. Conversion of the various limits to equivalent SI values and using appropriate rounding methods provides some flexibility in determining the final conversion value. Therefore only approximate values are offered for the SI figures so not to imply that these values represent “approved” or “accepted” values by regulatory or standard setting organizations outside the USA.
Bibliography
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© 2012 Springer-Verlag Berlin Heidelberg
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Prince, R. (2012). Operational Radiation Protection. In: Radiation Protection at Light Water Reactors. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-28388-8_6
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DOI: https://doi.org/10.1007/978-3-642-28388-8_6
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