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Appendix CRF - Part 3 - Northamptonshire County Council

Appendix CRF - Part 3 - Northamptonshire County Council

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The approach drives the correct behaviour down to the consignor in respect of<br />

the waste hierarchy because the approach enables remaining nuclide capacity<br />

(hence price) to be directly related to the environmental risk of that nuclide.<br />

The approach addresses the optimisation principle because the remaining<br />

capacity of the landfill is continuously optimised in a manner that ensures the<br />

overall risk guidance levels are not exceeded and the model will enable the<br />

operator and regulator to make informed choices.<br />

The capacity of the landfill is administered in a manner that ensures dose limits<br />

and constraints will not be exceeded with a significant safety factor to account for<br />

uncertainties.<br />

The approach maintains flexibility to account for the uncertain overall inventory of<br />

decommissioning wastes to be produced as required by regulatory guidance (ref<br />

19).<br />

8.16.7 For the purposes of authorisation this approach can be described as maintaining<br />

a condition in which the remaining radiological capacity for a particular nuclide or<br />

wastestream, which is proposed for receipt, is greater than zero, taking into<br />

account the wastestream received to that point in time. Where:<br />

Radiological capacity is the amount of radioactive material that can be consigned<br />

to a site without any of the potentially exposed groups considered receiving a<br />

dose above a specified criterion, for the specific scenario.<br />

For a single radionuclide, the radiological capacity (in Bq) can be easily<br />

calculated by dividing the dose criterion (expressed in Sv) by the maximum<br />

specific dose for that radionuclide (expressed in Sv/Bq). For mixtures of<br />

individual radionuclides, the capacity can be simply apportioned (e.g., half of the<br />

overall capacity to each of two radionuclides). In the case of waste streams,<br />

however, in which the proportions of different radionuclides are fixed, the<br />

calculation of capacity must consider both the specific dose and the activity<br />

ratios.<br />

The radiological capacity for radionuclide Rni in a waste stream (RCi) is given by:<br />

RC<br />

i<br />

where:<br />

<br />

<br />

DC<br />

i <br />

SD<br />

f<br />

Application for disposal of LLW including HV-VLLW under RSA 1993,<br />

for the East Northants Resource Management Facility:<br />

Supporting Information<br />

f<br />

i<br />

i<br />

fi is the fraction of the overall activity arising from Rni (such that fi=1)<br />

SDi is the specific dose from Rni<br />

DC is the dose constraint<br />

Furthermore:<br />

Total activity limit for<br />

each radionuclide (Bq) = Dose Limit (Sv/y).Waste Activity (Bq)<br />

Dose Estimate (Sv/y)<br />

July 2009<br />

89<br />

WS010001/ENRMF/CONSAPP<strong>CRF</strong> 408

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