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Management of Commercially Generated Radioactive Waste - U.S. ...

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6.127<br />

TABLE 6.1.21. Annual Routine Radiological Occupational Dose<br />

Exposure, man-rem/plant-year<br />

Operation<br />

Facility Routine Maintenance Abnormal<br />

FRP (1) 220 220 10<br />

FRF-WTF (2) 220 220 10<br />

FFP (3) 230 230 10<br />

FFP-WTF (4) 90 90 3<br />

Reference Facility (1) and (3)<br />

P-T (1-4)<br />

The more significant <strong>of</strong> the postulated accidents have been analyzed as to the resulting<br />

effects on the plant workers. In general, individual worker exposure would exceed public ex-<br />

posure because <strong>of</strong> closeness to the accident. Isotopic differences between the two cycles<br />

would result in small differences in exposure, so there is negligible distinction between the<br />

Reference and the P-T cycle, except that the Reference Facility does not contain the two<br />

WTF's. The totals for the component facilities are presented in Table 6.1.23. The details<br />

<strong>of</strong> the accidents and other assumptions are given in Fullwood and Jackson (1980).<br />

Table 6.1.24 presents corresponding data for the non-occupational consequences <strong>of</strong> the<br />

postulated accidents.<br />

TABLE 6.1.22. Annual Routine Non-Occupational Dose<br />

Exposure, man-rem/plant year<br />

Process Stage Ref. Facility P-T<br />

FRP 680 730<br />

FRP-WTF - 5.3<br />

FFP 7 x 10-3 1.7 x 10- 2<br />

FFP-WTF - 0.55<br />

Totals 680 736

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