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CSA N288.1

Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities

active, Most Current
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Organization: CSA
Publication Date: 1 January 2020
Status: active
Page Count: 478
scope:

Facilities

These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines applicable to releases from many other nuclear facilities, including research reactors, radioisotope processing facilities, waste processing facilities such as incinerators, and power reactors other than those of CANDU design, subject to the limitations detailed in Clauses 1.2 to 1.8. Application to other types of facilities such as fuel fabrication plants and refineries is limited by the radionuclides considered here (see Clause 4.3). These Guidelines may be adapted to cover part of the needs of such facilities, but additional models or methodologies might be necessary for other parts. However, neither the radionuclides nor the models included in these Guidelines are complete enough to cover releases from sources such as uranium mines and mills, or permanent geologic disposal facilities. In addition, the pathways are incomplete for any facilities where extensive modelling of groundwater pathways is required.

Release paths

These Guidelines cover releases to the atmosphere and to surface water (both fresh and marine). They do not address releases to groundwater, although transfers from other media to groundwater wells and ponds are considered. Direct gamma irradiation from radioactivity inside the facility is not modelled because it does not involve a release.

Release duration

The methods specified in these Guidelines are designed for routine, continuous, low-level emissions.

They also apply to periodic, short-term releases (see Clause 8.2), provided that

a) the releases are controlled and associated with normal operations;

b) the release rate is roughly the same from event to event;

c) for atmospheric releases, the total release duration exceeds approximately 1000 h in the year; for aquatic releases, at least one or two releases occur in each month of the year; and

d) the releases occur randomly over time.

Where the requirement of Item d) is not met but the releases are known to occur at a particular time of day or year, these Guidelines apply only if the air (water) concentrations are calculated using the meteorological (hydrological) data in effect for that time.

Notes:

1) Where non-random releases are calculated using time-appropriate data, it might be possible to relax the conditions on the release frequencies.

2) Releases that do not meet these conditions can use another model, such as that specified in CSA N288.2 for atmospheric releases.

3) For some facilities, intermittent releases occur predictably as spikes on a continuous base release. Such releases can be considered part of routine emissions and included in the DRL without special treatment if the total activity released in intermittent form is less than approximately 30% of the total release from the facility. The 30% cut-off is considered a small fraction of the overall uncertainty of the DRL estimates.

Contaminants

These Guidelines apply to the radiation effects of radionuclides. They do not apply to chemicals or to the chemical toxicity of radionuclides.

Receptors

The model can be used to calculate doses or derive release limits for a representative person having the average characteristics of a group of individuals who, by reason of their location and habits, are likely to receive the highest exposures to a given radionuclide released from a particular source (see Clause 4.2). These Guidelines do not apply to nuclear energy workers (NEWs), or to non-NEWs working at a nuclear facility, who are assumed to be covered by on-site radiation protection programs. The DRLs calculated using the models specified in these Guidelines apply to human receptors only; however, the models can be used to support dose calculations for non-human biota.

Downwind distance of validity

These Guidelines are not applicable to receptors located close to a source affected by building-induced turbulence because the atmospheric dispersion model does not simulate the cavity that forms in the lee of the building. Because the cavity extends approximately three building heights downwind, these Guidelines apply only beyond this distance. Moreover, the dispersion model should be used with caution beyond an approximate distance of 20 km from the facility because the assumption of steadystate meteorological conditions implicit in the model becomes less valid at greater distances. This is not an issue in practice because the representative person is usually found closer to the facility than 20 km.

Site specificity

Local parameter values should be used wherever possible when applying models to a specific site. Where local values are not available, the default values given in these Guidelines for the region closest to the site of interest may be used. These regional values represent conditions at the main nuclear sites in Canada (i.e., Pickering/Darlington, Bruce, CRL, G-2, and Point Lepreau) but may be interpreted as default values for the regional areas of southern Ontario, western Ontario, eastern Ontario, Qu├ębec, and the Maritimes, respectively. Some items which make sites unique are: topography (e.g., escarpment, river valley, lake effect), proximity to water bodies, prevalent wind patterns, and surface roughness.

Level of complexity

Simpler approaches

The models specified in these Guidelines are comprehensive and in some cases include considerable detail. This level of complexity might not be warranted for all assessments. Less complex approaches, involving fewer pathways and/or less detail, might be appropriate under some circumstances. Any pathway that can be shown to not contribute significantly to the total dose may be neglected. In these cases, simpler models such as those described by the IAEA Safety Report Series No. 19 may be used, provided that justification for using a simpler approach is provided.

Note: For example, the following need not be considered:

a) radionuclides that are not released from the site of interest; and

b) pathways related to wells that are not used as a source of water by members of the public near the site.

Default transfer parameters

A simplified approach is available for application of these Guidelines without implementation of the models. Annex A lists default transfer parameters for each radionuclide for each pathway in the model, together with the assumptions made in calculating the values. If the assumptions hold for the application in question, these default values may be used to obtain estimates of the DRLs without implementing the model itself, as demonstrated in Annex B. This allows all of the models and parameter values in these Guidelines to be accessed in a simple way. Because conservative assumptions were made in calculating the default parameter values, the DRLs calculated using this approach will be more conservative than those obtained by implementing the model.

The default transfer parameters can also be applied to conduct an initial assessment, combined with a sensitivity analysis, to determine which pathways or radionuclides merit further efforts to reduce model uncertainty through the application of site-specific measurements (see CDG, Appendix J).

Terminology

In these Guidelines, "should" is used to express a recommendation or that which is advised but not required and "may" is used to express an option or that which is permissible within the limits of the Guidelines.

Document History

CSA N288.1
January 1, 2020
Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities
Facilities These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines...
January 1, 2020
Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities
Facilities These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
0 Introduction 0.1 Derived release limit (DRL) The DRL for a given radionuclide is the release rate that would cause an individual of the most highly exposed group to receive and be committed to a...
September 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
September 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
January 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
January 1, 1987
Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities
General This Standard applies to airborne and liquid effluents associated with the normal operation of CANDU Nuclear Power Plants. It provides guidelines and a methodology for calculating the upper...

References

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