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Safety_Series_041_1975 - gnssn - International Atomic Energy ...

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This publication is no longer valid<br />

Please see http://www.ns-iaea.org/standards/<br />

7 8 APPENDIX IV<br />

It must be emphasized that observance of the 'dose limits'<br />

is not enough to ensure adequate radiological protection. The<br />

ICRP recommends that the competent authority should limit releases<br />

to the environment to values below the 'radiological capacity' (i. e.<br />

to that release which corresponds to the dose limits). This derives<br />

from the concept of 'as low as is reasonably possible' (ICRP No. 22)<br />

and also allows for further installations, which should not be penalized<br />

as to their protection costs. It is thus possible to define a<br />

protection factor P = authorized release/radiological capacity, which<br />

must also be taken into account in monitoring. The working limits<br />

multiplied by this factor, DWL XP, are called Authorized Working<br />

Limits (AWL). Environmental monitoring should show that these<br />

AWL values are being observed.<br />

COMMISSION OF THE EUROPEAN COMMUNITIES<br />

Environmental monitoring programme of the Ispra Establishment<br />

1. Radioactive effluents of the Ispra Establishment<br />

The Ispra Establishment of the Joint Research Center of the<br />

European Communities covers an area of about 1.5 km and includes<br />

few large installations and several laboratories (see Fig. 7). The<br />

main facilities are three nuclear reactors (Ispra-1, ECO and<br />

ESSOR), a hot laboratory for metallurgical studies of irradiated<br />

materials (LMA) and radiochemistry and radiobiology laboratories.<br />

The operation of these installations involves the production of radioactive<br />

wastes, part of which is released into the environment<br />

directly (gaseous effluents) or after decontamination treatment<br />

(liquid effluents). The solid wastes deriving from the latter process<br />

as well as from other operations are sealed into suitable containers<br />

(tar or concrete) and stored on the soil or buried into pits filled<br />

with concrete.<br />

The radioactive liquid effluents produced at the various facilities<br />

are sent to a treatment station, where they undergo a decontamination<br />

process and then are released into the sewer system of the<br />

Establishment. The volume of these effluents fluctuates around<br />

2000 m3/a and the overall activity ranges from a few tens to a few<br />

hundreds of mCi/a, mainly due to 137 Cs, 60Co and 90Sr. The<br />

discharge is not continuous and consists of 20 to 40 single release<br />

operations per year.

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