REPUBLIQUE FRANCAISE

INSTITUTE OF RADIATION PROTECTION AND NUCLEAR SAFETY

DEPARTMENT OF HUMAN RADIOLOGICAL PROTECTION

DEPARTMENT OF REACTOR SAFETY

Applicant DSIN (today the French Nuclear Safety Authority ASN)
Reference of the request

Note DSIN-FAR/SD4/n° 40405 /99 of April 16, 1999

EVALUATION GUIDE FOR THE RADIOLOGICAL IMPACT STUDY OF A BASIC
NUCLEAR INSTALLATION (BNI) AS A SUPPORT FOR THE AUTHORIZATIONAPPLICATION OF RELEASES
Mr. Chartier, A. Després, S. Supervil, D. Conte,
P. Hubert, A. Oudiz, D. Champion
Report/IRSN/02-24

October 2002

EVALUATION GUIDE FOR THE RADIOLOGICAL IMPACT STUDY OF A BASIC
NUCLEAR INSTALLATION (BNI)AS A SUPPORT FOR
THE AUTHORIZATION APPLICATION OF RELEASESTABLE OF CONTENTSSYNTHESIS OF THE DOCUMENT
1.

INTRODUCTION

2.

THE REGULATORY BACKGROUND

2.1. The decree n° 95-540 of 4 May 1995 modified an d the implementation texts
2.1.1Impact of the modified decree of 4 May 1995
2.1.2.Impact of the notice of May 20, 1998
2.1.3.Impact of the decree of November 26, 1999 and the implementation notice
January 17, 2002
2.2. Book II of title 1 of the environment Code (law on water) and theimplementation texts
2.3. Euratom directives 96/29 known as “basic standards” and the transposition
into the French legislation
2.4. Recommendations of the report “Radiological impact study on the public of
the nuclear facilities under normal operation”
3.
DESCRIPTION OF FACILITIES PRODUCING EFFLUENTS AND THE
TERMS OF PROCESSING, CONTROL AND DISCHARGE OF EFFLUENTS JUSTIFICATION OF
PROCESSING AND
MANAGEMENT RULES OF
EFFLUENTS
3.1. The aimed objectives
3.2. Description of facilities generating radioactive effluents
3.2.1. Facilities at the origin of the radioactive effluents
3.2.2.Reception of radioactive effluents coming from other facilities
3.2.3.Facilities leading to exposure of the public by direct radiation
3.2.4.Summary of the produced effluents

3.3. Description of the conditions of collecting, processing and release ofeffluents
3.3.1.Collecting effluents
3.3.2.Liquid waste processing
3.3.3.Characteristics of the effluents after processing
3.3.4.Conditions for the discharge of effluents
3.3.5.Analyzing and control of discharged effluents
3.4. Application of the operator and summary of the potential releases into theenvironment
3.4.1.The license application for the discharge of radioactive effluents
3.4.2.Best estimates and margins
3.4.3. Studies relating to several basic nuclear facilities (BNF)
3.4.4.Summary of releases into the environment
3.5. Choice justification for processing and management conditions of theeffluents to reduce releases
4.

DESCRIPTION OF THE ENVIRONMENT

4.1. The area covered by the environment description
4.2. Description of the natural environment
4.2.1. Climatology
4.2.2. Geography - Topography
4.2.3. Geology
4.2.4. Pedology
4.2.5. Hydrogeology
4.2.6. Continental hydrology (for example releases in a river)4.2.7. Hydrography, study of currents (for example releases at sea)
4.2.8. Biotope (natural flora and fauna) and ecosystem
4.2.9. Parks, natural reserves, ZNIEFF
4.3. Description of the economic and agricultural environment
4.3.1. Economic activities
4.3.2. Agriculture - Breeding – Agri-food industry
4.3.3. Fish - aquaculture - shellfish farming
4.3.4. Use of water
4.3.5. Other uses of water
4.4. Description of the demographic environment
4.4.1. Demography
4.4.2. Habitat, activities and practices
4.4.3. Dietary patterns and respiratory flows
5.

ESTIMATE OF THE RADIOLOGICAL IMPACT OF THE RELEASES

5.1. Radiological reference state
5.1.1. General principles
5.1.2.Case of an installation planned in a place without any nuclear activity: conceptof “point zero” 38
5.1.3. For example an installation planned in an existing nuclear site

5.1.4. For example an installation or an existing nuclear site
5.2. Suitable time scales
5.3. Choice and description of impact calculation conditions
5.3.1.Census of the transfer pathways in the environment and of the exposure
pathways
5.3.2. Census of the reference groups
5.3.3. Atmospheric dispersion of gaseous effluents
5.3.4. Dispersion of liquid waste in rivers
5.3.5. Dispersion at sea of liquid waste
5.3.6. Transfer of radio nuclides in terrestrial areas
5.3.7. Transfer of radio nuclides in aquatic areas (fluvial or marine)
5.3.8. Assessment of the integrated activities and the corresponding doses
involved
5.3.9. Assessment of the received doses by external exposure by individuals of
the reference groups
5.3.10 Dose summations
5.4. Presentation of the results
5.4.1. Results in terms of compartment contamination of the environment
5.4.2. Dose comparison within regulatory limits
5.5. Sensitivity and uncertainty - calculation of the impact of the expected
releases
5.5.1. Sensitivity and uncertainty
5.5.2. Doses due to the expected releases
6.

DEFINITION OF THE MONITORING SYSTEM OF THE ENVIRONMENT

6.1. Selecting the analyses to be carried out
6.2. Selecting the samples to be carried out
6.2.1.Terrestrial environment
6.2.2.Aquatic environment
6.3. Locating measurement points
6.4. Frequency of sampling and measurements

SYNTHESIS OF THE DOCUMENTAt the time of a licence application of effluent releases and water pumping of basic
nuclear facilities (BNI), the operator of the installation must in particular provide aradiological impact study of the radioactive effluent releases coming from theinstallation on the environment and on pubic health. By definition, it is about anassessment (in principle called an impact study ) corresponding with the future activityof the installation, even if such licence applications relate mostly to existing facilities
taking into account the Regulatory requirements.
An impact study of the radioactive releases represents technical and conditional
specifications. It was for this reason that the French Safety Authority (ASN then DSIN)
and the Directorate-General of Health Services (DGS) requested IRSN (then IPSN), in
April 1999, to develop a guide facilitating the review of such a study, as well for theservices implied in the examination of the licence applications, as for all the concerned
parties in this field.
A first version of this guide was issued (in the form of a project) in August 2001 by the
ASN. The present version takes into account all comments collected.
In order to guide the reader and to draw his attention to the major points, a summary isprovided hereafter.
The objective of the guide is to take into account the regulatory context which underlies
the development of the impact studies. The context is mainly made up of two texts:− decree n° 95-540 of May 4, 1995 (modified by the d ecree n° 2002-460 of April 4,2002) relating to releases of liquid and gaseous effluents and of water pumpingof BNFs and their corresponding application texts dealing with documents andprocedures as well as the required technical specifications for, in particular, thereleases of radioactive effluents;− The guideline Euratom 96/29 of May 13, 1996, known as “the basic standard
guideline”, accompanied by its transposition texts in French law, concerning thebasic standards relating to the health protection of the population and theworkers against the dangers resulting from the ionizing radiation. These texts
specify the concepts and sizes necessary for the assessment of received doses
by exposed people, as well as the basic rules of radiation protection to respect,in particular concerning optimization procedures to limit exposure and to respect
dose limits.
The guide also shows the recommendations made in January 1997 by a working group
created by the Directorate-General of Health Services, concerning the radiologicalimpact study on the population of nuclear facilities under normal operation.
In this precise context, the guide proposes to assess the radiological impact study of a
BNF from three different angles:−

the description and the quantification of the produced effluents, by taking
account of the triggering processes, of the different processing measures andof the procedures to optimise the reduction of the produced effluents;−the estimate of the dosimetric impact of the planned releases on the population,
taking into account the environmental characteristics of the installation;−

the definition of the conditions to monitor the releases and the environment.

This guide provides a general condition logical framework adaptable to any particularsituation met.
1) The description and the quantification of the produced effluentsIn the scope of assessing in a realistic way the impact of the radioactive effluent
releases of an installation, it is advisable to identify the root cause, to characterize thecomposition and to describe the effluent release conditions. This information is also
used as a support to optimise effluent management.
• The origin of the effluents: it is important to establish first an inventory of thevarious effluent producing spots (upstream of any processing before release),
specifying the nature, the mode of producing (permanent or occasional), thecomposition (produced radionuclides and corresponding activities), thephysicochemical characteristics, etc of each effluent. Description also refers to
the provisions taken to channel the effluents towards installations processingthese effluents, while mentioning, if necessary, the possibilities of diffuse
emissions of radionuclides. The inventory must also indicate possible
contributions of effluents coming from external facilities, as well as facilities
being able to lead to an exposure of the public by direct radiation. A summary
makes it possible to identify (from a qualitative and quantitative point of view)
the various categories of radioactive effluents and consequently determine their
management modes before release.
• The management of the effluents: it is important to describe, for eachcategory of identified effluents, the conditions of collecting and processing, byspecifying the selected choice, in particular based on the best available
technology at a economically acceptable cost. The characteristics of theeffluents before release have to be specified. Lastly, the conditions of analysis
and monitoring of the released effluents have to be described.
The result of this description of the conditions is a qualification as precise as possibleof the released effluents, providing the necessary elements to assess the impact, as
well as an accurate redaction of the license application for the release indicating, foreach category of radionuclides, the annual activities likely to be released. In general,
the operator includes in his estimate a margin, taking account of the normal
fluctuations of the operating installation (please remind that incidental or accidental
releases are not taken into account by release authorizations), of uncertainties on theestimate of the expected releases and uncertainties on control and counting
possibilities of the radioactivity of the releases. It is important that the selected margin
is clarified in such a way that it is able to justify, in particular, the actuality of therelease level described in the impact study.
Lastly, the description of the origin and the management mode of the radioactive
effluents is used as support to apply the optimization rule concerning exposure of the
public, in compliance with the “basic standards” guideline “; in this respect the operator
may take actions to reduce the activity levels of the releases, to direct certain
radionuclides towards liquid or gaseous releases, to choose processing technologies
limiting the release of radionuclides.

The optimization approach leads to choices based on multiple criteria such as technicalfeasibility, the safety of the process, the economic costs, the annual effective dose forthe reference groups, the collective dose of the population, the exposure of workers due
to effluent processing, the different kinds and quantities of produced waste.
2) The description of the environment of the facilities
The description of the environment will make it possible to identify the possible
pathways of transfer of the radionuclides present in the releases as well as each groupof people who, within the population, could form a reference group, i.e. groups forwhich the exposures coming from the facilities considered are relatively homogeneous
and which are representative for people who are receiving the highest doses due to theoperating facilities.
The following components of the natural environment should be described:−

weather conditions near the facilities (crucial for the spreading of the gaseous
releases);−

the topography of the locations (influence of relief in the spreading of thegaseous releases);−geology, pedology and hydrogeology in the proximity of the site (characteristicsof the soil, in particular in connection with their agricultural interest;
characteristics of the ground water, in particular in terms of vulnerability);−

continental hydrology (description of the discharge system of effluents in thecase of releases in a river) or marine hydrography and the study of currents (forexample by releases at sea);−

Biotopes and sensitive ecosystems, if necessary associated with natural
reserves.

The purpose of the description of the economic environment is mainly to identify
human activities that could be affected by the radioactive releases (for example tourist
activities) or that could lead to radioactive releases likely to expose the same
population as those concerned with the releases of the facilities considered.
The description of agricultural practices, breeding, agri-food industry, pisciculture (fishfarming), etc. under the influence of radioactive releases is particularly importantbecause it makes it possible to identify the various pathways to contaminate thehuman being via food. The same applies to human activities using water likely to beaffected by liquid radio active releases, whether it is surface water or ground water, forexample water used for irrigation or for the production of drinking water.
Finally the description of the human environment refers to:−demography around the facilities or in the areas subjected to the influence ofliquid releases (situation of residence, occupation, leisure , school, etc… areas)−characteristics of the habitat, practices of the population (specifying attendancetime of the people in the zones subjected to the influence of the releases);−- data on the dietary patterns (by taking into account as much as possible thelocal practices) and of the respiratory flows according to the age and the activityof each individual.

3) The estimate of the dosimetric impact on the population
The assessment of the estimate of the dosimetric impact of the releases on the
population depends on the one hand on the characteristics of the released effluents andon the other hand on the characteristics of the natural environment from an agricultural,
economic and human point of view. It is carried out in compliance with the radiologicalreference state, established starting from measurements in the environment andrepresentative of the radioactivity level of the environment at the time when the studyof the estimated impact is carried out. The main purpose of this reference state is to put
in prospect the impact of all future releases of the installation, within the framework ofposterior monitoring.
The estimate of the expected impact must also take account of the possible
phenomenon of radionuclide build-up in certain areas of the environment, and must
therefore be carried out over one period corresponding to the maximum build-up.
The calculation itself requires the use of computer codes identified and adapted to thedifferent inventoried pathways of transfer, namely:- The atmospheric dispersion of the gaseous releases, by taking into account theweather conditions and of the physicochemical form of the radionuclides. The
calculation permits to estimate the exposure by external irradiation due to a plume not
only by inhalation, but also by the radioactive rainout on soil and plants;- The dispersion of liquid effluents released into the aquatic environment (river or sea
currents), by taking into account the interactions with radioactive aerosols andradioactive sediments;- Transfer of radionuclides (and if necessary build-up) in the terrestrial section ( acontamination of the soil will start a chain reaction i.e. a plant- transfer eaten bybreeding stock animals and transfer to plants and animals eaten by human beings, etc)
due to the radionuclides deposited on the surface (via atmospheric fall-outs andpossibly via a seawater spray or via irrigation water);- transfers to the aquatic environment area (transfers to depth or bank sediments,
transfers to fish, molluscs and shellfish, transfers to the algae, seaweeds etc) will
determine a possible transfers to the human being (via for example drinking water, theconsumption of seafood and sea salt )This approach results in estimating the activity of the incorporated radionuclides andtheir corresponding doses involved for individuals of the identified reference groups,
but also the external exposure of these people (by external exposure due to the plume,
to deposits on the ground, to sediments, even by direct irradiation by the concerned
installation).
The annual doses received by individuals of each reference group are estimated by the
total amount of all the doses received due to liquid as well as gaseous discharges. An
estimate is also provided of the expected contamination in certain areas involved in thetransfer of released radionuclides, the estimate permits to direct the monitoring after the
event.

If necessary, the results of this assessment lead to further calculation studies for eachparameter that has a significant impact on the final result or that is the most uncertain to
define.
4)

The definition of the environmental monitoring system

Within the framework of the license application for radio active releases, theassessment study must also specify the monitoring system of the environment aroundthe installation, envisaged by the operator in order to be at the same time in compliancewith the regulatory requirements (Ministerial decree of the 26November 1999) and withthe characteristics of the releases and the environment of the installation resulting fromthe impact study.
The objectives of monitoring are the following:- To detect any failure in the discharge process (vigilance);- To make sure that the concentrations of radionuclides remain lower than thecalculated values estimated by the model of the radiological impact of the release- To highlight the evolution of the radioactivity of the various environment areas in thecourse of time.
It includes:- A continuous or regular monitoring which has primarily a role of alarm and of control;- periodic inspections making it possible to establish assessments of the contamination
environment in order to follow the variations of the concentrations in radionuclides on
the long-term; precise measurements will make it possible to supervise undetectableradionuclides within the framework of regular monitoring.
The installation of a monitoring system of the environment implies:- A selection of the studies to be carried out: immediate measurements or over a
period of time giving the average values over one period. These measurements should
not be limited to overall parameters, but must also relate to the most representative
radionuclides that are released with the effluents;- The selection of samples: the samples must come from different terrestrial areas(Air, soil, rainwater, plants, breeding stock and agri- foodstuff, etc) and aquatic areas(water, sediment, fish, molluscs, shellfish etc) likely to intervene in the radionuclidetransfers towards the human body;- The choice of localizing the measurements and the samples: measuring andsampling points are located as close as possible to the identified reference groups or
as close as possible to their activity area (fields, vegetable gardens, meadows,…)
Sampling at atmospheric concentration points and with maximum deposits is strongly
recommended;−

The sampling and measuring frequency: the frequency must be adapted to theperiodicity of the releases and to the activity level related to each monitoredarea (for example, in the harvest period of vegetables).

Specifying the releases•

Origin of the effluents•Management of the effluents•

Optimization of protection

Specifying the environment•

Natural•Agricultural•

Economic•

Human

Transfer towards the human body•••

Identifying the transfer pathways
Identifying the possible referencegroupsModelling of the dispersion and theradionuclide transfers

Dosimetric impact on Man

Environmental monitoring system•

Exposure by the intake ofradionuclides•

Choice of the parameters to bestudied•

Exposure by external
contamination•

Choice of the samples••
Calculation of received dose rateby the reference groups

Location and frequency oftaking samples andmeasurements

Summary of the general assessment approach of the dosimetric impact of
releases of a basic nuclear installation, in support of a license application todischarge/release

1.

INTRODUCTION

This guide was developed by the Institute of Protection against radiation and Nuclear
Safety (IRSN) on the request of the Nuclear Safety Authority (ASN then DSIN)and
Directorate-General of Health Services (DGS) in April 1999, in order to facilitate theassessment of the files concerning license applications for releases and water
pumping filed by the operators of basic nuclear installations (BNI) especiallyconcerning the discharge of liquid and gaseous effluents and the corresponding studyof their radiological impact. Please note that the guide does not cover the Impact ofchemical toxic releases however other documents issued by for example INERIS will
facilitate the assessment of this particular aspect. INERIS is a French public researchbody of an industrial and commercial character, founded in 1990 under the aegis of theFrench Ministry for Ecology, sustainable Development and Spatial Planning.
The first objective of this guide is to permit the concerned public services in charge ofthe review of these applications to check that the submitted files contain the necessary
explicit and conclusive elements necessary to estimate the expected impact due to theradioactive liquid and gaseous effluents. It offers a condition logical base, without
however going into the detailed calculation rules as they are already defined by theInternational Commission on Radiological Protection (ICRP) and included in thecomputer codes usually used.
In addition the guide will not only provide information but also add to a better
understanding for all the concerning parties (operators, elected officials, the populationin the surroundings of the installations, associations, members of local informationcommittees, etc) of the general approach on assessing a priori the radiological impactof an installation within the framework of a review of license applications by theauthorities.
In the scope of the objectives the guide takes into account the Regulatory context,
mainly specified by the decree n° 95-540 of 4 May 1 995 relating to liquid and gaseous
effluent releases and to water pumping of the basic nuclear facilities and also by theradiation protection requirements specified in the Euratom guideline96/29 of May 13,
1996, translated into French law is notably specified in decree n°2002-460 from 4 April
2002 relative to the general protection of people against the dangers of ionizing
radiation. In addition the guide takes account of the recommendations made in the
document “the study of the radiological impact on the population of nuclear facilities
under normal operation “, published in 2000 by the Directorate-General of HealthServices.
A first version of this guide, under the reference of IPSN/01-18, was given in August
2001 to the ASN and to the DGS, with the purpose to consult the public services
involved with the review of the license applications, but also the operators who havethe responsibility to forward the studies concerning the radiological impact of their
nuclear facilities in normal operation, in support of their license application.
The consultation was concluded by a presentation of the guide organized on May 21,
2002 by the new Directorate-General of Nuclear Safety and Radiation Protection(DGSNR), from now on in charge of the review of the license applications fordischarges and water pumping of the BNIs at a national level. The main observations
resulting from this consultation were taken into account in the present version of theguide.

Lastly, it is important to highlight that this guide provides general conditions that should
be adapted to the particular situations met. Also, for any given installation, thedevelopment of the various issues dealt with in this guide must be related to theimportance they present for the understanding of the installation’s impact on theenvironment. Elements that do not seem to be important for the concerned installationmust however be mentioned but without providing excessive details.

2.

REGULATORY CONTEXT

2.1.

The decree n° 95-540 of 4 May 1995 modified an d its regulations

The authorizations to discharge radioactive effluents of the BNF are granted pursuant todecree n° 95-540 of 4 May 1995 (modified by the dec ree n° 2002-460 of April 4, 2002),
related to the discharge of liquid and gaseous effluents and with the pumping of waterby the BNF. These authorizations are inter ministerial decrees (ministers in charge ofindustry, of environment, of health services) covering at the same time the field of water
pumping and releasing radio active and non radio active effluents.
Within the framework of this guide, only the aspects related to radioactive discharges/
releases are assessed, without prejudice concerning requirements specified by thedecree of May 4, 1995 concerning water pumping and the discharge of chemical
substances present in liquid or gaseous effluents.
The application of the decree modified the 4th of May 1995 is specified by two different
texts:The inter ministerial notice of May 20, 1998 concerning the review of thelicense applications within the framework of the decree n° 95-540 of 4 May 1995 related
to the discharge of liquid and gaseous effluents and to the pumping of water by Basic
Nuclear Installations (BNI).
The inter ministerial decree of 26 November 1999 specifying generaltechnical specifications related to the limits and the terms for Basic Nuclear Installations(BNI) regarding the discharge of effluents and water pumping subjected to authorisationand declaration; comments concerning the implementation of the decree are stated ina notice issued on January 17, 2002.
These various texts have a direct impact on the contents of the radiological impact
studies for Basic Nuclear Installations (BNI), specified herein.
2.1.1. Impact of the modified decree (4 May 1995)
The main articles of the modified decree of 4 May 1995 likely to have an impact on theradiological impact study are the following:
Art 8: the application includes:
Art 8-3°): “Nature, consistency, the volume and the object of the work, theinstallation, the works or activities considered, as well as articles attached to the abovereferred decree n° 93-743 of 29 March 1993 in which they must be classified.
Concerning the discharge process, the application indicates, for each installation, thevarious types of effluents to be treated and their respective origins, their quantity, theirchemical as well as their radio active composition, their physical characteristics, theprocessing used, the conditions under which the discharges take place in theenvironment as well as the composition of the effluents to be discharged “.
The implementation of this article forces to specify the quantities and compositions ofeffluents, by explaining their origins, and also their treatment and discharge process.
When several installations are concerned with the impact study, their above-mentioned
characteristics must be provided for each installation separately. (cf §3.2 and 3.4).
Art 8-4°): a document specifying the impact of the process on the water
resource, the aquatic environment, the water flow, the level and the quality of water,
including flooding due to seasonal and climatic variations as well as on each element
mentioned in article 2 of the above referred law of January 3, 1992, in function of theprocesses implemented, the operation or activity process, of the operation of the works
or the installations, nature, the origin and the volume of the used or concerned water.
If necessary, this document also specifies, by taking into account the seasonal andclimatic variations, the impacts of the operation on the quality of the air, odours, healthor public safety, agricultural production, conservation of buildings and of monuments, oron the character of the sites, and more generally on all the environmental components.
Indirect impacts, such as aerosol or dust fallouts or their deposits must also be
specified .Radionuclide transfers by the different pathways, in particular the food chain
and the aquatic sediments, are assessed and subject of a dose rate estimate to which
the population is submitted on a reference group level (decree N° 2002-460).
The document specifies, when required, the compensatory measures or corrective
actions considered and the justification of the project with the directing diagram or the
diagram of installation and management of water in the scope of preserving the qualityof water specified by the above referred decree of December 19, 1991.
If this information is given in an impact study, this information will replace the document
required in the present 4° ".
The requirements of this article will force the operator to present, in his license
application file a document concerning the impact. In addition the BNIs are subjected tothe modified law requirements n° 76-629 of July 10 concerning the protection of theenvironment and the corresponding modified implementation decree n° 77-1141 of
October 12, 1977 this document is normally replaced by an impact study, according to
the form stipulated in this last decree. In addition, as far as the radiological impact
analysis is concerned, the present guide is written in such away that it is equallyapplicable to the impact document quoted by the decree of May 4, 1995 or with theimpact study as defined by the decree of 12 October 1977 already mentioned above.
Art the 8-last subparagraph: “… The studies and documents stipulated in
the present article concern the whole range of installations or equipment in operation or
in development by the applicant which, by their proximity or their connection with the
installation subject to authorization, are likely to have an impact on the aquatic
environment or on water or on the atmosphere. “In addition of what is stipulated above in connection with the article 8-3°), thissubparagraph compels to take into account the impact on the aquatic environment or
the atmosphere due to the activities carried out near the installation mentioned in thelicense application of the request for authorization.

In practice, this requirement forces to assess also the radiological impact on theenvironment due to installations build on the same site.
2.1.2. Impact of the notice of May 20, 1998
The notice of May 20, 1998, pursuant to the decree of May 4, 1995, deals specificallywith the review of the license applications within the framework of this decree and does
not treat, as such, directly a radiological impact study. However, this notice contains
certain precise details being able to have an impact, in particular on the perimeter of thestudy:
from chapter I, one is requested to use in priority the possibility, offered by
the decree of May 4, 1995, “to gather in only one application all the operations subject
to an authorization or a declaration, should be carried out by the operator at the same
site,” ,in order not to divide the file and to allow the administration, the elected officials
and the public to have an overview of the expected operations on the same site, andconsequently their environmental impact;-

in chapter III § 2, it is specified that, if the request concerns a modification
on an existing site, the renewal of an authorization or a situation requiring a
regularization, “the information should be provided in the file pursuant to article 8 of thedecree of May 4 1995 and must as well concern the whole site” , including operations
already authorized, at least with regard to their direct proximity or functional link; theobjective is to be able to evaluate the impact of the operations stipulated in theapplication in relation with the rest of the site, especially if the effluents go throughvarious installations inside or outside the perimeter of the BNI before being discharged;
The same chapter, stipulates also that “the level of detail” to provide in thelicense application file must permit the department charged with the review and thevarious government administrations and services consulted, to assess the project, andthe detailed description must be in proportion with the importance of the impact of thedischarged effluents”.
2.1.3. Impact of the decree of November 26, 1999 and its implementation noticeof January 17, 2002
Articles 8 and 15 of the decree of November 26 1999 set similar general principles,
respectively on gaseous effluents and liquid effluents.
Please find a reminder and some comments on the effluents hereafter:- Uncontrolled radioactive discharges are prohibited;- The installations are designed, operated and maintained in order to limit theireffluent releases in the environment. The notice of January 17, 2002 specifies that “thisprinciple must lead the operator of a BNI to privilege clean technologies, substantiallylimiting, as much upstream as possible, the production of polluting releases. The
implementation of this principle must be in such a way that actions resulting in reducing
the quantity or the harmfulness of the produced effluents do not generate waste of anature or a quantity more inconvenient than the elimination of the effluents”;- These effluents must, as far as possible, be collected at the source, channelled
and, if necessary1, processed so that the corresponding discharges are maintained as
low as reasonably possible. The notice of January 17, 2002 specifies that “this principleforces the operator to reduce these discharges based on good practice of effluent
management. Apart from the use of adapted technologies, this principle applications apermanent control of the effluent management system. This principle is stated in sucha way that it allows the operator to take into consideration all the factors (economic,
safety of processes and of people and in particular the dose rates likely to be received,
pollution transfers,…) in order to determine the way to manage the effluents withinreasonable limits”;
1 Article 11- of the decree stipulates that all radioactive gaseous effluents are to be filtered or treated before release.

- The decree of authorization specifies discharge limits based on the use of thebest available technologies at a cost economically acceptable and the particularcharacteristics of the site environment. The notice of January 172002 specifies that“generally, this principle leads to set release limits based on good practices in force for
effluent management; that requires a good knowledge, on behalf of the operator, of the
production mode and of liquid waste processing according to the various operatingstates of the installations… The reference to the acceptable economic cost introduces arelative dimension that becomes logical by comparing several solutions based ontechno-economic study. In the case of an existing installation, this approach may be
applied in order to reduce the importance or the harmfulness of certain releases, by
evaluating the technical feasibility and the economic impact of the different possible
pathways; as far as new installations are concerned only the most recent state of theart in the considered field will be taken into account “;
These general principles have direct consequences on the way of describing the
installations at the origin of the effluents as well as the conditions of management of the
produced effluents, upstream from the assessment of the impact of the released
effluents. This has been taken into account in chapter 3.
In addition, articles 9 and 16 of the decree of November 26 1999 specify the different
categories of radionuclides for which a limit is set. The license application file must
therefore provide all the relevant information concerning these different categories ofradionuclides, as a reminder of paragraph 4.1 of the notice of January 17, 2002.
The decree of November 26, 1999 sets also different rules concerning the conditions ofeffluents discharges, which are likely to influence the radiological impact calculation.
Lastly, the articles 14-I and 22-II stipulate the monitoring of the radioactivity in theenvironment to be ensured by the operator, in particular to monitor the real radiologicalimpact of the installations. Therefore the license application file must specify theplanned monitoring conditions within this framework. The notice of January 17, 2002 (§9) states three objectives for this monitoring: to ensure a close monitoring of the effluent
releases and of their dispersion in the receiving environment; to monitor the possible
contamination of the environment; to contribute to the estimate of the dosimetric impactof the releases on the human being, in complement of the controls carried out by theauthorities.
Among the comments stated in the notice of January 17, 2002, it is also important
to mention the following (§ 1.4): “when the effluents are not discharged by the
producing BNI, but transported towards another installation outside the site to bedischarged there, a discharge authorization will not be necessary for the producing
installation. On the other hand, the transported effluent is a liquid waste to be treated ina specialized installation (BNI or ICPE), duly authorized for this purpose “. The precisionmeans that, in the assessment of the radiological impact of the releases of a BNI, only
the effluents actually released into the environment of the installation are taken into
account, this excludes all effluents transported to and treated in an installation ofanother site.
2.2. Book II title 1 of the environmental Act (law on water) and the applicationtexts
In addition to the modified decree n° 95-540 of 4 M ay 1995, other texts coming from themodified Water Act n° 92-3 of January 3, 1992 on wa ter are likely to have an influenceon the contents of the radiological impact study. This Water Act is responsible for thecreation of notably, 2 new planning tools: the SDAGE (control planning and water
management) and SAGE (development plans and water management).
The SDAGE specifies, for each catchment area basic guidelines of a balanced
management of water resources concerning the quality and the quantity, in the public
interest and in compliance with the principles of the Water Act; the second diagram(SAGE) specifies in particular, if necessary in a way compatible with the SDAGE
relating to them, the general objectives of the quantitative and qualitative protection of
surface and underground water resources. Decisions taken by the administrative
authorities with regard to water and aquatic environments must be compatible or bemade compatible with the provisions and guidelines of the SDAGE and the SAGE. Thisapplies in particular to the discharge of liquid effluents of a BNI towards an environment
covered by SAGE or a SDAGE, as stipulated in article 8 of the modified decree n° 95540 of 4 May 1995.
In practice, in the event of liquid radioactive releases, the license application file must
provide a demonstration of compatibility with the SDAGE and the SAGE, in case one ofthese planning tools stipulates specific provisions on radioactivity present in the aquatic
environment of the surface or underground.
2.3. The guideline Euratom 96/29 known as “basic standards” and its
transposition texts
The Euratom guideline 96/29 of May 13, 1996, known as the guideline “basic
standards”, specifies the basic standards concerning the health protection of the
population and the workers against all dangers resulting from exposure. The guideline
replaces the former guidelines dealing with the same issue and imposes theimplementation in the Member States before May 13, 2000.
In France, the transposition of this guideline is about to be completed (current situation:
the transposition of the guideline is completed); concerning the present guide, it isappropriated to mention the order n° 2001-270 of Ma rch 28 2001 introduced into the
French texts, in particular the public health code, the legislative provisions coming fromthe guideline, and the decree n°2002-460 of 4 April 2002 concerning the generalprotection of the public against the dangers of the ionizing radiation, replacing from now
on the decree n° 66-450 of June 20 1966 covering th e same issue.
Radiation protection regulations stated by the guideline and included in the French
legislative and regulatory texts are the following:- The exposures are maintained at the lowest reasonably possible level, taking
into account the economic and social factors (principle of optimization);- The sum of the effective dose received by a public person because of different
practices will not exceed the limit of 1 mSv per year (principle of the individual dose
limit);- The assessment of the effective dose is from now on based on the values andcorrelations defined by the guideline. These values are about to be adopted in France
through ministerial decree in preparation in accordance with article R. 43-5 of the publichealth code;- The doses are estimated with an approach as realistic as possible for the whole
population and for their corresponding reference groups, by including in particular: 1) inthe event of doses due to external exposure with an indication of the quality of theradiations in question; 2) the intake of radionuclides with an indication of their nature
and, if necessary, of their physical and chemical state and activity and concentration
specifications of the concerned radionuclides.
The guideline, just like the decree of April 4, 2002, defines the public as people, who
are not exposed to ionizing radiation:- In the purpose of a diagnosis or a medical treatment (patients or people whoare voluntarily exposed for their health benefit);- In the purpose of medical and biomedical research programs;- In the purpose of their intervention in the event of an emergency, to which apply
particular provisions;- For professional reasons requiring the use of ionizing radiation.
2.4. Recommendations of the report concerning “radiological Impact study on
the workers of a nuclear installations under normal operation “
Recommendations concerning the assessment of the dosimetric impact of liquid andgaseous radioactive effluent releases of the BNI were issued in January 1997 by aworking group created by the Directorate-General of Health. The report issued by theworking group was submitted and discussed within the section “radiation protection” ofthe French Superior Health Counsel and the report was officially published3 in 2000.
These recommendations emphasise in particular the following points:- The dose, in practice the effective dose, is the indicator of the best adapted
medical impact;- There are two main dosimetric impact studies: estimating impact studies
carried out upstream starting from the expected future release and impact studies
carried out afterwards ,starting from the measurement of the actual released
radioactivity complemented if necessary by measurements of radioactivity in theenvironment;- The assessment of the impact of a nuclear installation concerns not only thereleases by the identified outflows (chimneys, water discharge pipes into a river or thesea) but also the type of release (liquid or gaseous) and of the existence of radiation
sources present in the installation;- The source of exposure must be specified in the best possible way and ascomplete as possible concerning all qualitative and quantitative characteristics. It mustin particular contain the main actual released radionuclides and not only a conventional
list. The working group strongly recommends assessing the impact of direct radiation
coming from the installation;- Groups that may form reference groups (farms, villages, cities…) should beselected among the actual groups of people; by taking into account all the different
impact modes and all the different exposure pathways. The composition, the location,
the size and the way of life of the reference groups must be selected in a realistic way;
however, efforts spend on data acquisition must correspond with the importance of the
expected dosimetric impact;- The calculation and probabilistic traceability should be ensured by the use of arealistic approach and not a conservative approach; in order to place the impact of theconcerned installation compared to the annual dose limit , it is advisable to take into
account the impact of other related human activities likely to expose the public to
ionizing radiation and all the possible exposure pathways;- Special attention must be paid to the process of possible build-up on the longterm of certain radionuclides in the ground and in sediments;- Te file issued by the operator must show that the operator has planned thenecessary means and devices to reduce ,the dosimetric impact of the installation, tovalues as low as reasonably possible, taking into account the economic and social
factors. The operator must in this respect justify each choice by taking into account the
average individual effective dose in the different reference groups, the collective dose
(calculated over a circumscribed zone and over a suitable period of time), doses
received by the workers, the volume and the radio activity rate of produced solid waste
and investment and operating costs.
The working group recommends strongly a development of the impact studies by taking
into consideration the following requirements:- The traceability of the assessment (by checking if the measurements in theenvironment are representative, if the reference groups and their corresponding habits
are valid as well as the relevance of the models);- The contribution of the doses (contributions of different radioactive sources andof different exposure pathways).

3.
DESCRIPTION OF THE INSTALLATIONS AT THE ORIGIN OF EFFLUENTS
AND OF THE TREATMENT, CONTROL AND DISCHARGE CONDITIONS OF THE
EFFLUENTS - JUSTIFICATION OF EFFLUENT PROCESSING AND EFFLUENTMANAGEMENT RULES
3.1.

Objectives of this part of the file

The file as a support for the license application provides the description of theinstallations at the origin of effluents and the conditions of collection, treatment, control
and discharge of effluents, in order to be able to address the requirements specified inthe 3° of article 8 of the decree n°95-540 of May 4 , 1995. This description relatesparticularly to:- he identification, the description and the location of installations, works andactivities at the origin of effluents, to be considered in the requested authorization;- A characterization of the radioactive effluents expected to be released and their
management mode;- A description of all the outlets and in addition in the case of liquid effluent
releases into the aquatic environment, an identification of the receiving areas.
The file provides the justification of the characteristics of the expected effluent releases,
considering the processes that are implemented based on the best technologies
available for economically acceptable costs and the sensitivity or the restrictions related
to the direct environment of the installations.
Of course, the descriptions provided in this part must be in conformity with the safety
requirements for the installations in question (safety report, general operating rules,
general presentation of the safety of the establishment). When the file refers to an
installation already in activity, the different descriptions and justifications will specificallybe taking into account the operating experience feedback of the concerned installation.
Obviously all the probabilities must be, generally speaking, clearly exposed; theaccepted options as well as the negligible character of certain aspects must be
explained and proved.
Note: the license application file should give: a description of installations producing
non radioactive effluents, of water pumping activities and more generally speaking adescription of the installations, works, or activities justifying an authorization pursuant to
the decree of May 4, 1995 and its corresponding texts. However these aspects are notconsidered in this guide, because the guide only deals with the radiological impact on
the environment and on Man.
3.2.

Description of the installations at the origin of the radioactive effluentsThe file provides a description of each situation for example:- Installations at the origin of effluents;- Effluents coming from other installations of the same site (not concerned by thelicence application given in the file) and going through the installations concerned by
the application (for example, in the case of a liquid waste treatment station);- Installations that, although they do not produce radioactive waste, involve
however an exposure of the public by the radiation they emit (for example, the storageof radioactive sources).
N.B.: In accordance with the indications of the notice of January 17, 2002, the usedeffluent term in this guide indicates the liquid or gas products intended to bedischarged, normally after treatment, in the immediate environment of the site wherethese effluents are produced, by the installation given in the file or another installation at
the same site.
3.2.1. Installations at the origin of radioactive waste
All workshops, installations and activities at the origin of radioactive waste, even if it isoccasionally, included in the perimeter of the considered BNI, have to be described indetail. In the scope of having a detailed inventory of the elementary, permanent oroccasional fluxes producing the rough effluents intend for treatment. Each flux ischaracterized by its nature, its mode of production, its flow (or its quantity), theinventory of the different kinds of radionuclides with the corresponding activities, thephysicochemical characteristics of importance (for example pH, temperature) and thephysicochemical forms of the radionuclides, if necessary for the impact calculations (forexample, for C14, the mineral or organic forms). This description refers to:- Installations or workshops, the different functions and operations that are
carried out there, the operating mode (operations continuous or in series…);- The characteristics of the present material or implementations in each
installation or workshop in order to identify as comprehensive as possible the sourcesof radioactivity in the perimeter of the BNI, including waste (solid or liquids) coming frominstallations other than the ones described in the license application, are to bereviewed. This inventory includes the radionuclides generated within the installations by
the process (fission products or of activation products) or by radioactive by-products.
Specific details are provided on the different forms of radionuclides present in the
installation, their activities and their treatment and furthermore to explain the productionof radioactive effluents, the physicochemical nature of the products needed for theprocess or stored in installations (for example, the type of fuel used in a nuclear
reactor).
The radionuclide characteristics provided in the file are representative at the same timeof the average operation over one year, of possible variations from one year to theother and design limits of the installations or operating limits required by the technicalspecifications for operation. When these characteristics vary in time or are unplanned
but known, indications in terms of amplitude and frequency should be provided;- The physicochemical changes implemented in each installation or workshop, ina simplified way in order to follow the flux of radioactivity throughout the whole process.
This is in the scope to identify, the ratio of active flux to be found in the effluents, from aqualitative and quantitative point of view. Assessment of this ratio of active flux is basedon assumptions possibly checked by control points, concerning the division of theradionuclides during different elementary stages of the process (treatments of the
products, separations, phase changes, chemical changes,…) the assessment takes
also into account the possible recycling operations, reclassification of the radio active
flux as well as stages of long-term storage (by taking into account the radioactive
decay). Occasional events (start-up operations, maintenance, cleaning…) are also
taken into account in this assessment. The organization of the flux, the transfers andthe outlet identifications” in the form of untreated effluents is shown, either entirely or
partly in diagrams or tables.
Note:1) The operator estimates, during the above assessment that diffused
radionuclides releases may occur. For example the following phenomena are describedsuch as resuspension of dust, gas releases etc., by specifying the points concerning,for example, stored packages, storage tanks, joints between buildings, the setting withthe air of circuits, etc, and quantifies them (by a theoretical evaluation if necessary), in a
way to justify the provisions taken to ensure safety in compliance with theinterministerial decree of November 26, 1999.
2) If the file refers to several BNIs of the same site operated by the same
operator, the above description must be carried out for each BNI individually, even if
their effluents are afterwards treated and released together. In addition connections
between installations, in terms of flux exchange, must be specified.
3.2.2. Reception of radioactive wastes coming from other installations
The application concerns all installations (for example, a liquid waste treatment station)
receiving effluents coming from other installations, the file must provide a detailed
description of the composure and the quantities (or flow) of the transported effluents, aswell as the conditions of this transport.
3.2.3. Installations involving an exposure of the public by direct radiation
Independently of any production of radioactive effluents, the file describes theinstallations and activities (generally storing or storage areas of radioactive products)
likely to involve an exposure of the public by direct irradiation. However, even if therelease authorisation procedure does not refer to this type of exposure, the impact on
the public should be assessed to apprehend the radiological impact of all the
installations to value the acceptable character of the impact due to the radioactive
releases. The file describes and classifies the installations or activities concerned, themaximum activities likely to be carried out in each installation and the associatedconsequences expressed in the form of dose rates according to the distance startingfrom the limits offsite. These indications will be used further to estimate the impact on
the public.
3.2.4. Summary of the produced effluents
Further to a full description, it is recommended to provide a summary of the different
categories of rough effluents (before any treatment), by distinguishing the liquid andgaseous effluents. In general, in addition to the radioactive component, this summary
takes also into account the physical and chemical characteristics of the effluents. To
establish this summary, it is useful to distinguish the different categories of effluents by
specifying qualitative and quantitative aspects, for example:- All effluents related to the process, classified according to their levels of activity;- Permanently released gaseous effluents related to the ventilation of thedifferent premises of the installation;- Gas effluents resulting from the process, in general directed towards decay
tanks before release;- Liquid effluents resulting from “active” tanks, generally directed towards astation of radioactive liquid waste treatment;

- Liquid effluents resulting from “suspected” tanks, directed, after possible
treatment, towards the general network of the so called “industrial” effluent collection,then released into the environment;- All liquid effluents coming from the so called non radioactive “washroom
facilities” (toilets, sinks, showers….) directed towards a biological treatment station;- Rain water to be controlled…
3.3. Description of the conditions of collection, treatment and discharge of thedifferent effluents
Descriptions concerning the following points are submitted in a separate way for liquid
effluents and for gaseous effluents.
3.3.1. The collection of effluents
For the different categories of the previously identified rough effluents, the application
file describes in detail all devices and conditions of collection, management andtransport of the effluents towards the storage and treatment centres before being
released into the environment. The conditions of effluent management will be justified,for example according to the quantity, to the physical-chemical characteristics or to thelevel of radio activity of the effluents. The application file will give a detailed descriptionof the equipment and measures taken to ensure a safe collection of the effluents(Choice of materials, controls, routine inspections, regular maintenance……)
3.3.2. Effluent treatments
The application file gives a detailed description of the different means of processing
effluents before discharge, by technical specifications of the equipment and processes
being used for the treatment of effluents (nature, capacity, limits, efficiency…). Whenthe treatment consists in storing the effluents for a certain amount of time in order toreduce the radio activity, the storage capacities and the time of storage are indicated forthe different effluent categories concerned.
The file explains the accepted criteria concerning the choice of different effluent
treatments based on the characteristics of the effluentsand the efficiency of theequipment used for the different specific treatments. Note that any absence oftreatment before discharge must be duly justified. Sometimes these accepted criteria
are based on the best available technology for an economically acceptable cost. The
process efficiency on the different effluents already treated is explained, not only interms of the reduction of radio activity but also concerning the final composition of theeffluents obtained after treatment. The final by-products resulting from a specifictreatment process are specified. If necessary, a possible exposure of workers inducedby the treatment process must be mentioned.
Lastly, the application file must give a full description of the provisions selected to checkthe performance and the efficiency of the treatment, based on the control of theradioactivity in the effluents.
If the effluents are treated in installations of a site depending on another operator, thefile will mention the convention (or the draft of the convention) stipulated in article 9 of
the modified decree n°95-540 of 4 May 1995, by spec ifying the main terms of thisconvention in particular regarding the transportation and monitoring conditions of theeffluents. The efficiency of the treatment processes of the different effluents ontransport is specified.

3.3.3. Characteristics of the effluents after treatment
A summation is provided of the different effluent categories as treated by the installation
concerned by the application or another installation on the same site, and ready to bereleased into the environment. The summation will notably reveal for each effluent
category, the nature, the physical-chemical characteristics, the quantity, volume or flowrate, a list of the radionuclides with their corresponding activity …
3.3.4. Release conditions for effluentsThe file describes the release conditions for each effluent category, by specifying:- The characteristics of the outlet: chimney (position, height, release speed, flow
rate…); vent pipe; discharge system in a river, at sea, etc (a complete description of thereceiving environment, the position of the discharge system and the possible provisions
and devices facilitating the dispersion…);- If needed, the use of effluent dilution before release (this process should not be
considered as a treatment but as a measurement, applied only as an extra support for
the required treatments, with the intention to facilitate dilution in the environment), by
specifying the obtained results;- Effluent release conditions (by an uninterrupted flow or by emptying a completetank at once, flow rates, speed…) by indicating the parameters taken into account on
the moment of the effluent discharge (such as weather conditions in terms ofdissemination, speed or direction of the wind, conditions of the flow rate of a river’s
current, the quality (level of radioactivity) of the receiving aquatic environment, tides…).
Assumptions retained for the choice of conditions and their corresponding parameters
are clarified.
3.3.5. Analyzes and controls of the released effluentsThe file describes the nature of control and analyzes practiced on the released
effluents, by notably specifying the different types of measurements, their frequency,
their sensitivity as well as their decision threshold (or if needed, the limit of detection)and the corresponding alarms. The coherence between these controls and analyzes
and the characteristics of the releases concerned is demonstrated, in particularcompared to the different levels of release requested.
This description is made for each category of released effluents (processed gaseous or
liquid effluents, used water, rain water…) by specifying and justifying, according to eachcase:
- The type of control or measurement (uninterrupted, remotely, periodically, on
aliquot…);- The frequency or the due (expiration) date of the samples and measurements;- The measurement or sampling point;- The type of measurements or analyzes carried out (α, β, γ, total measurement
or spectrometric…) or the measured radionuclides, as well as the decision thresholds(or failing this, the detection limits) and, possibly, the corresponding alarms.
The file also specifies the conditions selected (control point, threshold of decision,
frequency of control) to check if certain radionuclides for which a release is not plannedin the effluent considered, are not detected after all. The file also mentions the
management operated in the event of exceeding a parameter or a selected limit value.
Generally, the file justifies the choice of analysis and control conditions of the releases,in order to be able to check if the releases carried out are in compliance with the values
indicated in the file, by taking into account the best technologies available for an
economically acceptable cost.
In addition, the file explains the principles and the conditions of accounting, in particular
for the very low activities, for the test results, as well as the operation carried out further
to these results.
3.4. The application of the operator and a summary of the releases carried out
in the environment
3.4.1. The authorization application for the release of radioactive effluentsThe file clearly reveals the application concerning the release of radioactive effluents.
The request mentions the types of effluents concerned (liquids, gas), the radionuclides
in question, annual activities likely to be released, even other characteristics of thereleased effluents if necessary. The application is drawn up in such a way that it takes
into account the categories of radionuclides defined in the above mentioned decree ofNovember 26 1999 (tritium, radioactive iodines, rare radioactive gases, carbon-14,
other beta and gamma transmitters, alpha transmitters…), by adapting them if
possible to the characteristics of the installation. The different categories selected in theapplication are justified.
The classification of the radionuclides or categories of radionuclides is clarified
according to the list of radionuclides selected in the preceding demonstrations, in order
to be able to calculate the dosimetric impact for the groups of reference considered.
The possible negligible character of certain releases will have to be demonstrated, if
necessary by a rough calculation of the dosimetric impact.
The possibility of an application evaluating with time may be taken into consideration(for example, an application corresponding to an installation before a planned
modification, and an application corresponding to the modified installation…). In thiscase, the study must deal with both phases (before and after modification).
Furthermore, the application may also be adaptable with time according to specificoperating modes distinguishing different release phases according to the nature and thequantity; for example, a test in an installation may produce a release of a particularcomposition for a relatively short time and being followed by long cleaning andrestoration works (decontamination, dismantling) because of the nature and thedifferent levels of activity of the effluents. In this last case, all the different operation
phases must be clearly described.
The file also reveals the application concerning the transport of radioactive effluents
towards other installations of the site. This application mentions the different types of
effluents concerned (liquids, gaseous), the radionuclides in question, the annualactivities likely to be transported, and if necessary other characteristics of thetransported effluents.

3.4.2. Best estimates and margins
Generally, data related to the released activities, submitted in the files, are best
estimates and they have to be as close to the realistic situation as possible. The
application for authorization is based on the expected levels of the release addressing
the real needs for the installation and if possible matching reasonable margins. Thesemargins are clarified, quantified and justified. They are never founded on incident or
accident situations, the authorized limits are exclusively based on a situation of normal
operation. These margins are taking into account the normal variations of operation of
the installation, by including all the possible regular maintenance operations, thevarious uncertainties related to the assessment of the expected releases, uncertainties
on the conditions of control and of total amount of radioactivity of the effluents (ifneeded, by relying on operating experience feedback), the planned modifications of theactivity of the installation (change of equipment, use of other fuels, etc), theuncertainties concerning the activity of the installation (for example, uncertainties on
experiments that will be carried out in the research laboratories in the future). These
different factors are in fact not cumulative because they do not intervene
simultaneously. Likewise, if the quantification of margins relies on the clarification ofdifferent operation scenarios, these scenarios will be best estimates and reasonably
realistic and consistent between them.
The variations and uncertainties related to the composition of the released effluents aredescribed in detail. The selected simplifications must be justified.
3.4.3. Example of studies related to several BNI
In the case of a radiological impact study file concerning several BNIs operated by thesame operator on the same site, the effluent release of each BNI has to be considered
preferably separately if possible (in general, the releases are authorized and regulated
for each BNI individually and if possible in the same decree). However, common
requirements are specified by the authorization for all the units of these BNIs and also
for all the other Classified Installations for Environment Protection (CIEP) in theneighbourhood of these BNIs. For example, the release levels for all the installations
together would have to be lower than the total of all the given release levels for each
installation (except for a duly justified impossibility), because of the non cumulative
character of the previously mentioned margins. In this respect, files concerning several
installations should reveal the accepted margins and the optimization related to releasemanagement of all the installations concerned without systematically cumulating the
given margins for each installation.
Note: taking into account the provisions (article 5) of the modified decree n°95-540 of
May 4, 1995, an application for the authorization of drawing (pumping) water and theconsequent releases only concerns Basic Nuclear Installations operated by the same
operator in a given place. When there are other BNIs or other Classified Installations(CIEP) owned by a different operator nearby the installations concerned, it iscompulsory for them to file their own application for an authorisation. However, it is very
important for the concerned installations to take the presence of other neighbouring
installations into consideration by the selection of release management of the BNIs,

subject to the application for authorisation (released activity, release conditions, longterm, short term, periodic, uninterrupted etc).

3.4.4. A recapitulative description of the releases into the environment
A recapitulative description should be made, for example in the form of a table in orderto have a global view of the radioactive releases into the environment. A global view isnecessary to calculate the dosimetric impact and to specify the release limits in theauthorization decree.
The description should in particular specify the nature of the different effluent releases,
the activities annually released corresponding with the different radionuclide
characteristics of each effluent, the maximum volumic activities, parameters
corresponding with the releases (flow rate, speed, physicochemical parameters…) andthe release conditions (outlets; activity flowrate). In addition the nature of the different
effluents transported from one installation to another installation nearby and theircorresponding activity annually released for the different radionuclide characteristics ofeach effluent transported should also be specified.
If the application concerns an existing installation, the file takes into account theoperation experience feedback, in terms of production and management of theeffluents. The file highlights the operating movements and fluctuations (evolutions) andall incidents that generated accidental releases not covered by a normal operation of
the installation. The requested release values are taking into account the detecting
limits of the assessment conditions like uncertainties related to measurement results. It
is always difficult to say if the measurement results entirely match or are entirely
representative.
3.5. Justification of the accepted effluent processes and management
conditions in order to reduce releases
General technical specifications of the above mentioned decree,of 26 November 1999,
applicable to the release authorisations of radioactive effluents by BNIs, are in particulardrawn up to match the regulations applying to classified industrial sites for theprotection of the environment (ICPE). In this respect, the decree forces to limit releases
by using the best technologies available for an economically acceptable cost, by taking
into account the specific environmental characteristics of the site. The application of thisprinciple aims at limiting the releases to the real needs of the installations in question.
In addition the decree specifies that the releases are maintained as little as reasonably
possible. These regulations force (art. 8 and 15) the operator to minimize his releases
thanks to careful effluent management in order to prevent or reduce the danger ofpollution4 and nuisance that the installation may present. The operator has to consider
the following aspects: technical performances, processing costs, the safety of personnel
and the population, guarantee the safety of the process. Within this framework, thedosimetric impact on the population constitutes one of the main aspects to consider.
4 In order to prevent that a process intended to reduce an effluent release leads to the production of other forms ofpollution or leads to problems due to a more important risk

Indeed, the optimization of the exposure of the population is a provision of theEuropean Directive on the basic standards 96/29. The article 6 stipulates that “eachmember State takes care… that in the context of optimization, all the exposures aremaintained at the lowest level reasonably possible, taking into account economic andsocial factors “. The so called “ALARA” (As Low As Reasonably Achievable) approach,concerning the optimisation of exposure by the BNI and ICPE installations “applies to:- The level of activity in the liquid and gaseous releases;- The preferential direction of the releases either into the atmosphere or into the aquatic
environment (river or sea)
- The used technology for treatment and management of effluents, allowing to reduce or
to avoid the release of undesired radionuclides because of their high dosimetric impact
on the environment;- Release conditions: for example, the right moment to release in order to optimize thecapacity of dispersion and dilution of the radionuclides into the atmosphere and into theaquatic environment (river, sea);- Direct external exposure, if necessary.
The file of the operator justifies the accepted technical options based on the overall
policy of maximum release reduction. The file shows a comparison of the advantages
and disadvantages in relation with the main solutions for:- Effluent flow management (triage at the source, separation of flows…);- The reduction of diffuse releases (not channelled);- The reduction of radioactivity of all the channelled releases: storage tanks, efficiencyof the means used for the treatment of liquid and gaseous effluents…
The operator should pay extra attention to the management and to the reduction ofcertain specific categories of radionuclides5 because of their major contribution to thedosimetric impact of the liquid or gaseous releases. The operator justifies the list of theradionuclides accepted in the optimization study, based on the calculation of thedosimetric impact. The experience feedback of the operator is used to complete thesafety demonstration.
The stakes are important; therefore systematic research is carried out to findalternatives for flow management, adopted processes or equipment. Possible solutions
are submitted. The comparison between the different technologies available will
determine with precision the chosen direction, based on the following criteria:
Technical feasibility, safety of the process, costs, annual effective doses for thereference groups, collective doses received by the population, exposure of the workers
due to the effluent treatment, the category and the quantity of the produced waste. The
choices are justified by a study proving that the adopted solutions are the best ones
among the different solutions considered. It is possible to base the safety demonstrationon the example of other similar installations in France or abroad. This study must also
show that the selected processes are in compliance with the protection of theenvironment set at a national or local level (Regulatory texts, charts for environmental
protection, large scale planning to avoid pollution SDAGE, WISE, analysis of the qualityof the air on a local level). Possible by-products due to the processing (mud, cinders,ashes…) is mentioned in the file.

When an installations is compelled to emit radiation leading directly to exposure of the
public off- Site (cf. § 3.2.3), the operator must explain the reason why and must justify
the doses received by the reverence groups , compared to the means he has at his
disposal to reduce or remove this type of exposure (screens, safety limits, etc.).

5 Because of the physicochemical similarity in behaviour that makes them inseparable from each other.

4.

DESCRIPTION OF THE ENVIRONMENT

4.1. The description covers an extensive field.
The environment description is extremely variable depending on the examined aspect(terrestrial environment, aquatic environment, economic and agricultural activities,
demography, etc). Therefore it is necessary to have a detailed description in order to
identify all the reference groups and to assess their risks of exposure. Accordingly, for
one given aspect of the environment, the number of details in the description may vary
according to a progressive zoning starting from the installation.
For the release of gaseous effluents, the reference groups are in general located withina radius of a few miles. This zone is under constant radiological environmental
monitoring and must be described in detail. The description of geographical areas at alarge distance from the installation considered is normally less detailed, even if the
impact of the gaseous effluent release is noticeable. In general, one may consider thatat a distance of about 10 to 30 kilometres, the impact of a gaseous effluent release
under normal circumstances is negligible.
For the liquid effluent releases in fresh water, the situations may vary. A joint
assessment of the major hydraulic characteristics (dams, junctions, interactions with thegroundwater, zones easily flooded,…) and of the different utilizations of the water inquestion is necessary to establish the geographical area of interest. However, thedescription will not only give a detailed description of the environment before thereleases but also after the releases, in order to get a clear view of the possible changes
in the natural environment due to the releases.
In general, a rather broad zone (possibly till the sea) of the aquatic environment of fresh
water should be covered, although the description will gradually be less detailed moving
away from the installation. Indeed, the spreading process is fast immediately
downstream from the outlet, but afterwards the volumic activity varies relatively little till
the sea due to the relatively-closed character of the aquatic environment. That is why
the continental aquatic environment contaminated by liquid releases is defined at
distances more important than those considered for the gaseous releases.
For the liquid effluent releases at sea, the situations vary a lot. A joint assessment ofhydraulic characteristics (topography of seabed and coast line, presence of islands
inhabited or not), of ecological characteristics (presence and abundance of the biotope,
development of specific ecosystems), current characteristics (tides, wind streams,
airstreams, surface waves), sediment characteristics and the way the environment isused by Man (fishing zones, zones of nautical leisure, pisciculture and shellfish farming)
will establish the geographical area of interest.
More indications on the different aspects of the description concerning the environmentof the installation will be provided here-after.

4.2.

Description of the natural environment

The objective of the description of the natural environment in this context is primarily tosupport the assessment of the radiological impact. All components of the naturalenvironment likely to influence the result of the calculation of the impact (selectedconditions, values of the parameters) are addressed.
4.2.1. Climatology
The dispersion of gaseous effluent releases is strongly influenced by weather
conditions. Therefore it is very important to have a precise knowledge of themeteorological processes occurring during the dispersion.
To quantify (by modeling) the dispersion of the gas releases, the turbulent diffusionmust be taken into account. In practice, different dissemination categories are specified
depending on the used model, for example normal dissemination and weak
dissemination, or a stable, unstable or neutral atmosphere.
How the deposit of the aerosols on the ground and on the vegetation takes place
depends on the weather condition, if it rains or not. It is advisable to determine with
precision
The pluviometry should be carefully determined (duration of the rain period, moment of
the year, average quantity of rainfall). If necessary, snowfall will also be examined.
The file must also provide detailed wind roses. In practice, it means that the windfrequency divided over a sector of 20° and the clas sification of the wind speed should
be provided (the number of different wind speed categories will be defined according to
the local climatology, but in general this number should be lower than 3). Assumptions
for the presentation of calm winds are specified.
The file gives a description of the combined frequencies of wind conditions (per sector
and wind speed category), the conditions of dispersion and the conditions with orwithout rainfall (snowfall).
These data are representative for an “average” year and are based on a compilation ofseveral years.
These data must be representative for the conditions close to the release points of thegas discharge. Horizontally, the data come from the site it self or a point a little bit
further away and representative of the conditions on site. Vertically, the data arecollected at chimney level (or at a point close to chimney level) and if necessary a little
bit higher than chimney level because of the extra height of the plume (due to“steam”jet and thermal effect).
For the assessment of dispersion on an average and long distance, it is important toknow the statistics of appearance and the height of the temperature change.
The relevant statistics of the main parameters for climatology are also submitted forexample: air temperatures (in particular the extremes ones), the humidity of the air (andin particular fog), exceptional events (storms, thunder storms,..).
4.2.2. Geography - Topography

A general description of the geography of the area and a more detailed description of
the local geography are submitted. Topography is specified, particularly the variationsof relief near the installations, in order to specify the modeling conditions of the gaseous
effluent dispersion (spreading)s. This description is accompanied by maps on relevant
scales.
4.2.3. Geology
A general description of the geology of the area and a more detailed description of thelocal geology are submitted. This description is accompanied by maps on relevant
scales. Relevant data concerning the substratum of the studied zone (the nature andthe presence of rocky formations at seabed level) are specified, in connection with thegeological description
4.2.4. Pedology
A classification table of the local soil and ground is submitted. The different ground andsoil categories are submitted, and in particular their agricultural interest and the different
types of natural vegetation growing on this soil. By soil used for agricultural activities(cultivation, breeding) all information on the grading, the level of organic matter, theirpH, the capacity of cation exchange, the levels of easily assimilated phosphorus andpotassium, has to be taken into account by the calculation of the radiological impact on
the population .
4.2.5. Hydrogeology
A description of all groundwater and their main characteristics (location, water conduit,
communication between groundwater and surface water, etc) is submitted. This
description is accompanied by maps on relevant scales. Quantified data are provided(the average groundwater level and the variability of the upper level of the groundwater,
flow rate, transfer capacity) as well as data on the physical properties (for example theresistivity, the hardness, the Ph and the temperature of the groundwater) and thechemical properties (for example bicarbonates, chlorides, nitrates, sulphates, sodium,
potassium, calcium, magnesium).
The vulnerability of the resource is examined, in connection with existing or future useof the groundwater.
If necessary, the file mentions all information related to the perimeters of protection ofdrinking-water supply stations located in places likely to be influenced by the radio
active liquid or gaseous effluent releases. (see also paragraph 4.3.4).
4.2.6. Continental hydrology (releases into a river)
A description of the discharge system(s) of the liquid releases is submitted, from thesource till the sea. This description is accompanied by a map on relevant scales. The
file gives a detailed description of the profile and the mode (particularly the tides, highand low water levels) of the rivers, the drained surface, all the different installations likedykes, pipelines, dams and possible flooding. All possible exchanges with ground water
are indicated.
The nature of the basic sediments of the rivers (grading and mineralogicalcharacteristics) and the dynamic of their deposits are specified.

The detailed description concerns especially the environment close to the installation,
but may also concern more remote situations, for example other human activities inconnection with the release of radionuclides upstream or downstream from theinstallation, or other activities using the aquatic environment like irrigation by farmers,
using the river for the drinking water supply and for leisure purposes like swimming etc..
4.2.7. Hydrography, courantology (for example release at sea)
A general description of the oceanic area is submitted: topography of seabed andcoastline, general description of dynamic movements of the currents, generalcirculation, a general description of the temperature and salinity gradient, the mainfeatures of the sediments, and if necessary the main influences generated by Man likelandscaping (creation of artificial beaches) constructions, pollution due to all thedifferent releases and eutrophication of water.
A more detailed local description is submitted giving a detailed topography, adescription of the beaches, the local movement of the currents (instantaneous andresidual tide, sea heaves, the variability and currents of the wind) , the spatiotemporal
temperature and salinity changes, a detailed description of the different sediments andtheir quantity and the presence of local pollution.
These descriptions are accompanied by maps on relevant scales.
The examination of local dispersion (mathematical model, mock -ups, field studies withtracers or buoys) is fully detailed.
4.2.8. Biotope (natural flora and fauna) and ecosystem
Fauna and the flora are described at a regional level in detail in particular on local level.
A detailed description of the terrestrial flora (arborescent flora, shrubby flora,
herbaceous flora, mushrooms, moss, ferns…) and the aquatic flora (brown algae, redand green, moss, mushrooms, ferns, plants with seeds…) is submitted.
A detailed description of the terrestrial fauna with a skeleton (batrachians, reptiles,
birds, also the migratory birds, mammals…) and without a skeleton (molluscs, insects,
moth, etc) as well as the aquatic fauna (fish, mammals, batrachians, plankton,
molluscs, shellfish, …) is submitted.
All fragile species sensitive to pollution or endangered species are quoted.
A brief description of the different ecosystems is submitted, in particular if the releases
are likely to reach ecosystems that are considered to be sensitive.
4.2.9. Parks, natural reserves, ZNIEFF
The existence of natural reserves, natural reserves, natural areas of ecological interest
fauna and flora ZNIEFF) in the zone under the influence of liquid and gaseous effluent
releases has to be indicated. In addition the main characteristics and the main
perimeters of these areas are specified.
Please find below a short explanation of the French acronym ZNIEFF!
The acronym stands for: Natural Area of Ecological Interest, Fauna and Flora.

A ZNIEFF is part of the territory particularly interesting from the ecological to themaintenance of large balances or constituting the natural living environment of animals
and rare plant, characteristics of natural regions.
There are two types of ZNIEFFs:
ZNIEFF ( type I ), is in general a limited area, defined by the presence of endangered
species and associations of species or environments with rare or outstanding naturalfeatures of great biological and ecological interest on national or regional level.
ZNIEFF (the type II) are in general large natural rich areas slightly modified by Man,
however they are still providing an important biological potential. The areas of type II
may include one or more areas of type I
Together these two types of zones (type I and II combined) cover 46 % of the regionalsurface. This is the highest proportion among the regions of France. This wide varietyof environments is linked to the diversity of climatic influences Mediterranean, Atlantic
and Continental as well as reliefs and regional geological features.
The inventory of ZNIEFF identifies, locates and describes the heritage of sites ofinterest for species and habitats. It streamlines the collection and management of dataon the natural environment, fauna and flora. Prepared for the Ministry of theEnvironment, it is the main tool of scientific knowledge of natural heritage and is thebasis for the definition of political nature. It has no direct legal value but allows a better
consideration of the rich heritage in the development of projects likely to have an impact
on the natural environment. Therefore, the failure to take into account a ZNIEFF at thedevelopment phase of a project like for example a Basic Nuclear Installation would be amanifest error of assessment an may be subject to appeal. The ZNIEFF constitute abasis for the development of a nature policy, especially for the most sensitive wetlands,
moorlands etc ...
4.3.

Description of the economic and agricultural environment

The objective of the economic and agricultural environment description in this scope isprimarily the support of the assessment of impact. Only components of economic andagricultural environment likely to influence the result of the calculation of impact are
mentioned. All elements with no influence on the impact are simply avoided.
4.3.1. Economic activities
A general presentation of the regional and local economy is made. Especially industrial
activities are described (the nature of the activities, the importance of subcontracting,numbers of workers, planned evolutions,…). The description might reveal very different
situations. The environment should be assessed under several economic angles in asuitable geographical area. Therefore the following points are described in detail:- All activities (industry, hospital, etc) contributing with their radioactive releases
to the risk of exposure of the population must be mentioned because it will imply
restraining the quantity of the to be authorised releases of the installation considered;- In addition, all economic activities potentially affected by the releases of theinstallation (in particular the ones using the same environment that will receive theeffluents) should be described. For example tourist activities are described, in particular
by indicating a possible seasonal increase of the population people in the closesurroundings of the installations concerned (camp-sites, beaches for example) likely to
be exposed to the releases of the installations.

4.3.2. Agriculture - Breeding – Agri-food industry
Agricultural activities, activities of breeding and economic activities in relation to theagri-food industry are described at a regional level and they have to be extremely
detailed in the geographical area close to the installation, in order to provide relevant
data for the dosimetric impact calculations for the reference groups. Please note that forgaseous effluent releases the described zone generally corresponds to larger areaaround the installation. In order to carry out dosimetric impact calculations for thereference groups and to provide useful data to assess the consequences of a possible
dysfunction of the gaseous effluent releases.
A full description is given of farming areas that are irrigated and or easily flooded byrivers receiving liquid effluent releases. The closer to the concerned installation the
more detailed the description has to be.
For liquid effluent releases at sea, a full description is given of all areas where collectionof algae or any other product used as a fertiliser for agricultural soil takes place.
A detailed description should also be given of the whole farming industry (dairy farming,
factory farming, intensive farming, single crop farming etc……)
The nature and importance of the industry, livestock, and occupation of the soil, thetransformations and the distribution of the industry are specified. The practices used are
mentioned (for example it should be clearly specified whether the agricultural
production is in an open field or in greenhouses, the different types of irrigation andsprinkling systems …). Whether the food production is continuous or variable from one
year to another must also be mentioned. The presence, the location and the number ofkitchen gardens and private orchards are specified, as well as the main plants, trees
and vegetables cultivated there.
4.3.3. Fishing – aquaculture (fish farming) - shellfish farming
Activities of fishing, activities of aquaculture and shellfish farming and economic
activities related to the agri-food industry are described on a regional level and evenmore detailed on a local level close to the concerned installation.
The nature and importance of the aquaculture and the shellfish farming and oyster
farming industry and of the fishing industry (the captured species and their quantity), thelocation of producing and the fishing areas at sea, the fishing harbours, thetransformations and the distribution of the products are specified. All aquaculture,
shellfish farming and fishing practices used are mentioned (in particular concerningseasonal workers).
4.3.4. The use of water
Only the use of water likely to be affected by the liquid releases (if necessary in case of
the gas releases after cleaning the soil) is concerned. For all installations releasing into
the river, the use of water is described in general downstream from the installation. For

the installations releasing at sea, only the area under the influence of the liquid releases
is concerned.
In case of releases into the river the description should cover a large area downstream
from the outlet, because of the variable conditions of the river’s situation that will have a
direct influence on the dilution and concentration of the radionuclides of the discharge(river junctions, exchanges of water with the ground water and retention ofradionuclides by sediments). Therefore description must be given of how and for what
purpose the water is used even far away from the outlet. However a more detailed
description must be provided for the use of water located at close distance from theinstallation.
The use of water for domestic reasons is described as followed: the use of surface orgroundwater, distribution networks, purification stations for the drinking water supply,
the corresponding quantities of water and if necessary the quality of untreated water.
This description is in general rather detailed because the use of domestic water is themost direct way to expose and contaminate the population, which has to be avoided at
all times
The use of water for industrial reasons is described as followed: the use of surface orground water, the different water treatments with their corresponding quantities of waterand the quality of untreated water is required.
The use of water for agricultural reasons is described as followed: the use of surface orground water with the corresponding quantities of water, how the water is usedsprinkling, irrigation with a pipeline system etc.., seasonal aspects, location and thekind of agricultural industry concerned. Generally this description is rather detailed
because the transfer of radionuclides into agricultural products may result in an
accumulation of the radionuclides.
4.3.5. Other uses of water
The possible use of water for fishing, leisure or tourism are described as followed:
swimming, water sports, hunting and fishing sports, food and flower picking… The
description covers the following locations: fields, riverbanks, beaches.
4.4.

Description of the demographic environment

The objective of the description of the demographic environment in this context isprimarily to support the impact assessment, in particular concerning the identificationand characterization of the reference groups. The level of necessary details varies
considerably according to the fact whether the populations are likely to be referencegroups or not. For areas that are less affected by the releases, from all the referencegroups only the most concerned are described, like a first assessment element for thecollective exposure due to the releases.
4.4.1. Demography
Demographic data are provided, for the gaseous and liquid effluent releases in acircular zone around the installation. In addition, all zones affected by liquid releases
must be specified especially in relation with the use of water for other purposes. The
data relate initially to the area close to the installation. Demographic data in this area
are very detailed because they are used for the determination of the reference groups.

The data are based on all scales from village to town or if possible even on a finer scale(hamlets, isolated farms, etc). These data concern not only the habitat but also the
population of workers (industrial parks, factories, workshops, administrative buildings),
and any other population (schools, tourists, etc). These data describe the structure of
the population in function of age, by detailing in particular the young population (infants,
young children, teenagers). The data are extremely precise in a radius of 10 miles fromthe concerned installation covering all villages and towns in this area.
Other data of demography are submitted on a broader scale (typical for gaseous
effluent releases is a radius of 50 km around the installation concerned). Only data
related with large groups of the population are indicated (for example, cities of morethan 10.000 inhabitants).
4.4.2. Habitat, activities and practices
In combination with the demographic data, data are provided related to the identified
population groups.
For the gas releases, these data concern the habitat (crowded or dispersed) and if
needed the work locations. These data also concern the parameters in relation with theactivities of this population that will have an influence on their risk of exposure to theradioactive releases (for example work in the fields, professional fishing at sea, nauticaland leisure activities, etc….).
These data concern finally all practices likely to modify the risk of exposure of the whole
population (for example, mushroom collecting, oysters, shellfish etc).
Data in connection with budget-time are associated with those concerning the habitat,
the activities and practices. It is a question of specifying the annual time spend by the
population concerned in areas likely to receive deposits of aerosols or sediments
containing radionuclides. These data are detailed according to the age groups of thesubcategories of the identified population.
These data are extremely detailed for the identified population groups (the residents or
the population groups whose activities are exerted in the zone) in the area close to thereleases, and only mentioned in a more general way in the other areas.
4.4.3. Dietary patterns and respiratory flow rates
All data concerning the dietary patterns of the identified population groups are provided,
primarily for the area nearby the releases. These data are required to establish all foodcategories likely to be contaminated. These data reflect as much as possible the local
food practices. These data are detailed according to the different age groups of theidentified subcategories of the population.
It may be useful if these data comprise several statistical elements (average
consumers, large-scale consumers).The origin of the consumed foodstuff is specified
as detailed as possible, especially the local origin of the products. In the same way, theorigin of drink water is specified. Any manipulation of the food products carried out by
the agri-food industry before consumption has to be specified.
Any publication reference concerning the results of respiratory flow rates from any
individual is mentioned. Because their use for the assessment of the relevant
respiratory flow rates of the individual reference groups is justified by the characteristics

of these groups (age groups, distribution men/women, activities, workers and seasonal
workers composition, etc…).

5.

THE ASSESSMENT OF THE RADIOLOGICAL IMPACT OF THE RELEASES

5.1.

Radiological reference state

The objective is to have a reference state covering all possible releases of radioactivity
in the environment. This reference state allows on fore hand to plan and organize future
monitoring of the environment in the environment and facilitates the follow-up of thecontamination induced by the installations concerned, by measuring the radioactivity inthe environment. Therefore it is very important to know the actual situation of theinstallation considered in the licence application for effluent releases. It has to be
specified whether:- The installation is isolated;- The installation is close to the releases of other installations. ;- The installation is in development (a future installation)- The installation already exists;- The installation modifies significantly the release before discharge (for example
the released radionuclides are modified before discharge).
5.1.1. General principles
It is important to determine the different areas of the environment that are likely to bemodified by the planned releases. What area to examine is a result of the impact studyof the planned releases (in particular the transfer path ways in the environment) and of
the description of natural, agricultural and demographic environment and if needed theeconomic situation of the site.
(See above).
The environment is divided over 3 areas of interest:- The representative dispersion areas of the effluents (mainly water, air);-The biological indicators representative of the biological accumulation processof radionuclides;- Areas important for the food chain.
The reference state includes all the elements necessary for each type of area.
Samples should preferably be chosen among the most representative composition of
the area (for example for the biological samples) or among the products that are used
for consumption, especially if they are locally consumed in one of the environment
categories. The selected areas must be monitored and checked year after year. The
sampling must be justified.
Sampling is carried out in zones defined according to a double logic:

- Zones affected by the releases (downstream of a river, zone under the wind) inorder to specify the variations of the radioactivity in the areas due to the releases. One
has to be sure that these zones are or will be actually affected by the releases (pollutionof the aquatic zone by a liquid effluent release or pollution of the atmosphere due to aplume);- Zones little or not affected by releases (upstream of a river, a distant zone in anarea without dominant winds) in order to define a reference point of reference likely to
be monitored later in order to be able to give even more details concerning the activity
source in the areas.
The sampling zones are justified according to this double logic. In this context, special
attention is paid to crowded zones.
The number of samples and measurements, carried out in the environment
representing the statistically reliable radiological state of the area, must be specified.
The period of sampling must also be adapted to the nature of the monitored
environment: for example, samples of cultivated plants are taken at the time of harvest.
The major sampling points are:
- At the river: samples are taken from the water of the river, (untreated water,
filtered water), sediments, water plants, fish, molluscs and biological indicators (algae,
moss, molluscs);- At sea: samples are taken from the water (untreated water, filtered water),sediments, water plants, fish, molluscs, shellfish and biological indicators (algae,molluscs);- In the terrestrial field: samples are taken from aerosols, rainwater, groundwater,
grass of permanent meadows, fodder, cultivated and not cultivated ground (soil), allproducts used for consumption by Man (cereals, vegetable-leaves, vegetable-fruits,
vegetable-roots, beef and veal and all aggri-food industry products like poultry and/or
porcine, eggs,… and processed products like wine) and biological indicators (moss,lichens, mushrooms, thyme, all dairy products like milk and by-products, in particular
cheese).
Please note that the natural ambient dose rate is also measured.
The analysis carried out on the samples allows characterizing in detail their
physicochemical and radioactive state.
The following analyzes are to be carried out:
- Physical analyzes (pH, particle-size distribution of soils and sediments);- Chemical analyzes of the characteristic components of water and sediments,
the level of potassium and calcium in terrestrial plants and fish;- Biometric analyzes for fish;- Spectrometry α;- Spectrometry γ;

- Measurements of 3H, 14C and 90Sr and if needed of other transmitters pure betaaccording to the future releases.
The quality of the radioactivity measurements must correspond to the required
monitoring objectives, by using the best measurement technology against an
economically acceptable cost.
Total measurements α and β may be carried out in order to have references for
operational monitoring of the installations, although they are not very useful for thedosimetric impact calculations.
The description of the environmental radioactivity reference state is completed by adescription of the dosimetric reference state of the site. The measured dose rates in theatmosphere must be specified on a map. These dose rates come from cosmic andterrestrial radiation, and sometimes from prior releases and deposits due to a nuclear
accident. Irradiation due to cosmic radiation depends on the altitude of the location.
Irradiation due to terrestrial radiation depends on the nature of ground and soil. It istherefore important to specify and demonstrate the situation of the direct environment of
the site by a number of appropriated measurements
5.1.2. Example of a future installation in a place with no nuclear power activities:
concept of “point zero”
The environmental radioactivity reference state of the environment without any
influence of a nuclear installation located nearby must be specified; a so called “pointzero” situation before the future installation;
All activities of artificial radionuclides spread in the atmosphere by nuclear weapon trials
and nuclear accidents (134Cs, 137Cs, 90Sr, 14C, 3H, 238Pu, 239Pu, 240Pu,…) are
specified.
All activities of artificial radionuclides in the aquatic environment due to nuclear weapon
trials, nuclear accidents but also due to any other installation that may affect theenvironment of the future installation are to be mentioned. Note that, the activity ofradionuclides is measured in the different areas of the aquatic environment, notably the
sediments.
5.1.3. Example of a future installation in an existing nuclear site
The environmental radioactivity reference state is partly described by the analysis of themonitoring results of existing installations located close to the future installation.
However routine measurements are not always sufficient to describe with precision thereference state. The detection thresholds of measurements may be insufficient. The
monitored areas of the environment around a site cover only a reduced part of all areas
necessary to get a clear description of the reference state.
Certain monitoring measurements (total of α and β) are not directly useful for thedosimetric impact calculation. For example around certain large sites , the referencegroups determined for the releases of all the existing installations may differ from thereference groups determined for the releases of the future installation. In addition
samplings carried out around a badly located site may not result in a relevant radiology
state reference for a future installation. Further analyses to complete the monitoring
results of the site are to be required. All releases from the future installation likely tocontain one or more specific radionuclides that are not already released before by theexisting installations on site should be specified.
5.1.4. Example of an existing installation or an existing nuclear site
A radioecological assessment of the environment around an installation or around a sitealready affected by prior releases must be carried out, in order to assess theradiological impact on the environment by former releases. The radiological impact has
to be specified as accurately as possible before validating of the models of radionuclidetransfer into the environment. It is important to note a possible accumulation ofradionuclides, in particular in the ground and in aquatic sediments. Dosimetric impact
studies of the releases considered must hold account of the accumulation if existenceof an accumulation has been proved.
The impact of any event taking place offsite, modifying the radioecological state of theenvironment since the initial determination of point zero, must be specified, for example
the impact of the Chernobyl accident.
Lastly, note that, the results coming from normal monitoring procedures of theenvironment are often insufficient to characterize the radiological reference state andextra sampling and analyses are to be carried out.
5.2.

Suitable time scalesThis question is particularly important for the correct treatment of the long- term
accumulation phenomenon.
The licence application for release exclusively relates to effluents releases that willtake place only after the delivery date of the authorization. In principle theauthorisation is granted for an unlimited time. The time period to be considered in theassessment of the radiological impact of the releases has to correspond to a period
during which no major evolution of the releases is planned (even with a higher or lower
level of release). In general, the duration to take into account is the residual operation
duration of the installation proposed by the operator.
Some exceptions call for a specific duration of the period. If for example significant
modifications of the releases are considered, shorter periods of authorization than thelifespan of the installation may be considered. A new application might be necessary
after the implantation of release modifications.
Concerning installations (or a group of installations) for which dismantling operations
are considered, generally generators of releases different from those produced innormal operation, it has to be specified if these operations and their duration are still incompliance with the requested authorization.
5.3.

Choice and description of the impact calculation methods

The calculation methods include not only an inventory of all the nuclide transfer
pathways in the environment and of all the contamination pathways of the population
but also an identification of the reference groups and the modelling of the exposure
starting from valid computer codes.
The values of the parameters used in the models are always justified, notably on thebasis of an environment description (values specific to the site) or on relevant scientific
literature (values nonspecific to the site).

5.3.1. Census of transfer pathways in the environment and of contamination
pathways of the population
All the possible pathways of radionuclides transfer are explored, starting from theeffluent discharge till the population, by covering not only the permanent pathways but
also the irregular or rare pathways. The whole population concerned is studied nomatter what age group. All forms of released radionuclides are studied. Especially thetwo main kinds of release are considered namely the gaseous and liquid effluent
releases.
All the contamination pathways (external exposure, internal exposure by ingestion andby inhalation) are explored. The synthesis of all these combinations (the whole
population, all transfer pathways, all contamination pathways) lead to a list ofsignificant pathways, although many different ways to recombine are generally
possible (by liquid and gas releases, categories of radionuclides, by different
categories of the population, by the main types of contamination pathways).
Minor transfer and contamination pathways, minor radionuclides may only be
neglected after a justification by global estimates.
5.3.2. Census of the reference group
A reference group is a group of individuals of the population for whom exposures
coming from a given source are relatively homogeneous and representative forindividuals receiving the highest dose coming from this source. Theoretically, it ispossible to define, for a given release source, one or several reference groups for eachpathway of transfer, each nuclide, each part of the population and each contamination
pathway. In practice, because of the recombining mentioned above the number ofpossible reference groups is generally restricted to a few groups. At this stage, nogroup of individuals that may form a reference group must be ignored, especiallybefore a dose calculation (even roughly).
Different criteria are considered to identify the reference groups. One can quote forexample the geographical criterion of proximity (inhabitants of a village near the
installation), socio-professional criteria (families of fishermen at sea), habits or
behaviour (summer visitors on a beach affected by radionuclides releases), age criteria(infants, adults, the elderly….) or a combination of these criteria. A thorough analysis of
the environment is generally a source of invaluable information for the identificationand the inventory of the reference groups.
Note: it should be noted that individuals, generally workers, who remain daily at anuclear site, even if they are not “ exposed workers” according to the regulations forradiation protection , are usually not taken into account in the definition of the referencegroups, within the framework of the license application for effluent releases of a BNI.
It is important to recall that the dose determines the relevant reference groups because
they must be representative of the most exposed individuals. At this stage of the study
it is important to have a thorough inventory based on the indications provided by astudy of the natural, economic, agricultural and demographic environment as alreadymentioned above(before complete and detailed calculations of the dose).
Apart from exceptions, this inventory does not stop with only one declared group,
without a preliminary demonstration, of the“obvious” reference group (for example avillage under dominant winds for the gas releases), for at least two reasons:
1. The identification of the most exposed reference groups sometimes proves tobe insufficient; knowledge of other less exposed but larger reference groups like young
people, more sustainable, etc is useful, in particular to identify the territory or the
populations under the influence of the releases. The information will help to define a
relevant framework for the monitoring of environment or simply to inform the public;
2. Taking into account of only one parameter to estimate the impact (for example
frequency of the wind directions for the example of dominant winds) is incorrect
because other parameters play also a prevailing part (frequency of the wind speeds,
stability conditions of the atmosphere, precipitations, etc) and may lead to higher
impacts for reference groups who were not really considered.
Only an impact calculation will permit to identify the most exposed reference groups.
However a global impact calculation might be sufficient to exclude groups who will beless exposed than other groups.
The size of the reference groups is often subject for discussion because there are no
general rules to apply. In fact a group consisting of only some individuals or on thecontrary a much larger group of individuals is both possible. It is the level of exposure(which must be sufficiently homogeneous within the group) that determines the size ofthe group. Please note that, the higher the dose the smaller the groups of the
population to examine in order to be able to identify the individuals. Notably if the
inhabitants are spread over a large area and are living rather isolated, it is strongly
recommended to identify the different groups of the population, a group may evenconsist of only a few individuals, living close to the highest concentration peaks ofpollution in the atmosphere due to gaseous effluents.
In addition, by the existence of a significant agglomeration close to an installation (forexample in a radius of 30 km), it is useful to present a calculation of the dosimetricimpact for the individuals of this agglomeration.
5.3.3. Dispersion of gas releases in the atmosphereA model of gaseous effluent dispersion is selected and described. Justifications of theselection are provided.
The simplified assumptions of this model, the known limits (for example for zones close
to the discharge outlet), the experiments for model validation are shown in detail (anypossible publication reference duly referred and accessible to all may be given; in thiscase, a summary of this information appears in the file). The physicochemical form of
the radionuclides taken into account is also mentioned.
Possible adaptations of the model to address the industrial site concerned aredescribed in detail.
The influence of the topography of the ground of the site or the presence of highbuildings is also discussed.
However it is possible to neglect the depletion of the plume.
5.3.4. Dispersion of liquid releases in rivers
A model of liquid effluent dispersion in rivers is selected and described.
Justifications of this selection are provided, in particular in relation with theenvironment (fishing, water sports, fish farming and shellfish farming…)

The simplified assumptions of this model, the known limits (for example for the flowrate of the river), experiments for model validation are shown in detail (any possible
publication reference duly referred and accessible to all may be given; in this case, asummary of this information appears in the file). That the physicochemical shape of theradionuclides is taken into account is also mentioned.
Interactions of the radionuclides with aerosols and sediments of the riverbed aremodelled if needed. The models and why they are selected are clarified. The possible
aspects of the kinetics of these interactions are mentioned.
5.3.5. Dispersion of liquid releases at sea
A model of dispersion at sea of the liquid effluents is chosen and described.
Justifications concerning the selection are provided, notably in relation to theenvironment (fishing, shellfish farming, nautical leisure,…).
The simplified assumptions of this model, the known limits (for example for certain tide
margins or specific weather conditions),), the experiments for model validation are
shown in detail (any possible publication reference duly referred and accessible to all
may be given; in this case, a summary of this information appears in the file). That thephysicochemical shape of the radionuclides is taken into account is also mentioned.
Interactions of the radionuclides with aerosols and sediments of the sea bed aremodelled if needed. The models and why they are selected are clarified. The possible
aspects of the kinetics of these interactions are mentioned.
5.3.6. Transfers into the different areas of the terrestrial environment
Models of transfer in the different areas of the terrestrial environment are selected anddescribed in detail (deposits on the ground, accumulation and transfers in the ground,transfers to plants used for consumption by the livestock, transfers to plants andanimals used for consumption by Man). Justifications of the selection are provided,
regarding the rejected radionuclides, the type of ground, the agricultural and local
industry etc.
The simplified assumptions of this model, the known limits (for example for theclassification of the different vegetables in main categories like root- vegetables, fruit,
leave vegetables like spinach and salads; the absence of differentiation between beef,
pork, sheep or horse meat; the assumption of a non existence of radionuclides) and all
experiments for model validation are shown in detail (any possible publicationreference duly referred and accessible to all may be given; in this case, a summary ofthis information appears in the file). The physicochemical form of the radionuclides
taken into account is also mentioned.
Models concerning specific radionuclides are fully detailed, in particular models oftransfer into the environment of radioactive hydrogen and carbon isotopes which arecomponents of life. The contamination level due to former activities of the installation (arelease history and a summary of former incidents) is taken into account in theassessment of the activity levels in the different areas of the whole terrestrial
environment.
5.3.7. Transfers into the different areas of the aquatic environment(River or sea)
Models of transfer in the different areas of the aquatic environment are selected anddescribed in detail (radionuclide tranfers into aerosols, on beaches and sea bed andcoastal sediments, contamination of fish, oysters, shellfish, mollusc and algae; possible
transfers into drinking water sea salt or salted sea water). Justifications of the selection
are provided, in relation with the grading of sand, beaches and sediments, the speciesof fish, molluscs, shellfish and algae concerned, etc.
The simplified assumptions of this model, the known limits (for example for theclassification of the different species in main categories like fish and seafood; theabsence of differentiation between fine and coarse sediments; the assumption of a nonsettlement of radionuclides on aerosols) and the experience in model validation are
shown in detail (any possible publication reference duly referred and accessible to all
may be given; in this case, a summary of this information appears in the file). The
physicochemical forms of the radionuclides taken into account are also mentioned.
Models concerning specific radionuclides are fully detailed, in particular models oftransfer into the environment of radioactive hydrogen and carbon isotopes which arecomponents of life.
The contamination level due to former activities of the installation (a release history
and a summary of former incidents) is taken into account in the assessment of theactivity levels in the different areas of the whole aquatic environment.
5.3.8. Assessment of activity intake and the corresponding dose rates
An estimate of the intake of activities by individuals of the reference groups is made in
general over a whole year, in order to apply the regulation because the main limits areannual. The selection of the year considered is justified, notably compared to thepossible phenomena of accumulation which could lead to different results according to
the selected year.
An estimate of the specific and volumic activities in food eaten by Man is made bytaking into account the modifications due to the transformations carried out in the agrifood industry and by the modes of culinary preparation of the dishes.
The activity intake through ingestion of the various radionuclides is calculated for eachindividual of the reference groups by taking into account their dietary patterns.
The activity intake through inhalation of the various radionuclides is calculated for eachindividual of the reference groups by using the respiratory flow rate and the time spentin the contaminated atmosphere.
The doses received through inhalation and ingestion is calculated starting from theactivity intake and the dose coefficients. The selected margins for the received doses
are clarified, notably according to the physicochemical form of the radionuclides
concerned and the age category of the population. Calculation conditions and factors
as well as the effective dose values involved per intake unit for each radionuclide,through ingestion or inhalation must be used in compliance with the regulation
pursuant to the R.43-5 article of the Public Health Code, must be used. If thecalculation of the required doses requires margins, which are not set by any regulation,these margins are selected in a suitable and justified way.
5.3.9. Dose assessment by external exposure received by individuals of thereference groups
Doses received through external exposure coming from plumes (in the air or in thewater), deposits on the ground or in the sea or river sediments are assessed foreachradionuclide and each reference group starting from the specific or volumic
activities added in the relevant areas, the time spent in the contaminated area of theindividuals and of the dose coefficients. The dose coefficients are clarified. Generally,
they come from scientific publications, which are mentioned in the file.
The estimate of activity intake is also clarified and also based on scientific publications,
mentioned in the file the assessment of external doses is carried out in general over a
year. The selection of the year is also justified and clarified.
If necessary, an assessment of the external exposure coming from the direct radiationfrom the installation is carried out specifically for individuals of the reference groups
concerned.
5.3.10.

Cumulative doses

The cumulative dose, concerning individuals of each reference group, which is the sumof all the doses received due to gaseous and liquid effluent releases, is given for all
radionuclides and all contamination pathways. If necessary this is added to thereceived doses through direct exposure because of the installation.
In the case of a study related to several installations (respectively in the case of one
installation part of several installations), this addition is carried out for each installation(respectively for the installation considered) and afterwards on all the installations
together.
5.4.

Presentation of the results

5.4.1. Results in terms of contamination in the different areas of the environment
All intermediate results related to contamination of the different areas of the terrestrial
and aquatic environment are provided, for all radionuclides.
This exhaustive presentation has two objectives:- To allow a double check independent of calculations;- To have a clear view of the order of magnitude of the expected maximum
contaminations, in order to check whether other regulations applicable to certain
products for human consumption are respected and to prepare the monitoring ofenvironment.
5.4.2. Comparison of the amounts in extreme cases lawful
The decree n°2002-460 of 4 April 2002 concerning th e general protection of the people
against the dangers of ionizing radiation defines the dose limits to be respected for all
individuals of the public. This decree imposes that the sum of the effective doses
concerned received in one year by an individual of the public likely to be exposed due
to Human activities should remain less than 1 mSv. The file compares, for eachreference group the annual doses received due to the releases if necessary the file will
also compare the exposure coming directly from an installation, limited to 1mSv by
taking into account the doses possibly received by individuals of the reference groups
due to other activities (notably from other installations close to the installation
concerned).
5.5. Sensitivity and uncertainty - calculation of the impact of the releases
expected

5.5.1. Sensitivity and uncertainty
In general, a certain number of simplified assumptions are adopted in the compositionof the released effluents, in the modelling of the transfers into the environment and in
the habits and the dietary patterns of the population. Certain parameters intervening in
calculations are slightly unknown. Moreover, it is frequent to adopt an approach ofimportance by the selection the simplified assumptions. Consequently the dose
calculation will always remain close but uncertain.
Although an analysis of complete uncertainty is not required in the file, it is preferable
that a sensitivity study concerning parameters with a direct impact on the dose and astudy of the most uncertain parameters is provided, notably for the maximum dose
estimate likely to be received by the population considering the uncertainties. Such ananalysis is to be carried according to the dosimetry stakes corresponding with thereleases, for example the margins of a radio ecologic transfer.
5.5.2. Doses due to the expected realistic releases
The release limits are generally defined by margins. Expected realistic releases forwhich the margins were not taken into account are generally significantly lower than thelimits. For a better understanding of the information by the public, the file specifies thedosimetric impact estimate of the releases without the margins. In practice, for existing
installations discharging without significant modifications of the effluent releases andsubject to the application of the ALARA approach(see§ 3.5), it is accepted to calculate
the doses based on the data of effluent releases of a recent year.
6.

DEFINITION OF THE MONITORING SYSTEM OF THE ENVIRONMENT

The modified decree n°95-540 of 4 May 1995 stipulat es that the license application for
effluent releases indicates the technical an human means of monitoring envisaged. In
addition, the decree of 26 November 1999 imposes the implementation, by theoperator, of a monitoring program for the radioactivity in the environment. The nature,
the frequency and location of the samples and the measurements are defined in theauthorization decree. The file accompanying the authorization application must thus
propose a monitoring system which will be taken into account in the definition of theregulations accompanying the authorization.
Generally, the measurements in the environment permit:- To detect dysfunctions in the release operations (vigilance);- To make sure that the concentrations of radionuclides remain lower than theestimated values in the modelling of the radiological impact of the releases that havebeen carried out.
- To highlight the evolution of radioactivity in the different areas of theenvironment in the course of time.
A normal monitoring procedure of the environment includes:- Continuous or regular monitoring primarily for control and alarm purposes;
which is the reason why it is carried out permanently;

- Periodic inspection visits making it possible to establish assessments of theenvironment contamination in order to follow the variations of the indicators of thecontamination on the long-term; meticulous measurements make it possible to monitor
undetectable radionuclides within the framework of regular monitoring.
Note: there are other types of measurements of the radioactivity in the environment,
apart from the normal monitoring procedures. These measurements are mainly used
after an accidental or incidental release and therefore not described in this guide.
However they improve the knowledge on the phenomena of transfer into theenvironment and on dosimetric assessment.
The monitoring system suggested in the licence application relates to the following:- The magnitude to be measured;- The selection of the samples;- Location of the measurement points;- Frequency of the measurements;- Presentation of the results.
6.1.

Selection of the analyzes to be realized

The analyzes to be carried out include instantaneous measurements (dose rate,
specific activity in a crop product,…), measurements integrated in time (measured
dose on a dosimetric film, daily sampling of rainwater,…) or average measurements
over a given period (volume activity of the air,…).
It is important to note that the monitoring of the radioactivity in the environment does not
only comprise total measurements (α total, β total) but must comprise the measured
activity of the radionuclides which are rejected by the installation concerned.
The radionuclides to be measured are to be defined according to the composition of thereleases; for example, gamma transmitters radionuclides of 14C, 90Sr, the I’ 129I, I’ 131I,
3
H linked and free, 238Pu, 239Pu + 240Pu, 241Am, 244Cm, and other radionuclides specificfor certain installations like 65Zn, 85Kr and 133Xe .
A certain number of physicochemical characteristics influence the capacity of thedifferent environments to settle the radioactivity. It is therefore necessary that thesecharacteristics are specified using complementary analyzes adapted to the studied
areas in order to be able to compare (in time or in space) the activity of identicalsamples:- For water, the pH, conductivity, the dissolved oxygen content, the majority of
cations and of anions;- For plants, the water content;- For the ground and the sediments, the grain size, the capacity of cationexchange.
6.2.

Selection of the samples

The samples are selected according to the nature of the relevant transfer pathways,
which have already been identified.
6.2.1. Terrestrial environment
The following areas of the terrestrial environment are to be monitored:- Air (gas and aerosols), grass, ground, rain and snowfall;- According to the local agri-food industry, the leave- vegetable (salads,
spinach,…), fruit-vegetables (tomatoes, beans, …), root- vegetables (potatoes,…),cereals (corn, corn, rice) and fruit.
Note: The selection is guided not only by food products intend to be sold for humanconsumption but also by food products coming from the vegetable gardens;- According to the local livestock products, milk (of cow and goat), beef, sheep,poultry meat, eggs, honey;- If necessary, all processed products (flour, wine, cider,…).
6.2.2. Aquatic environment
The normal monitoring procedure on inland water is focused on the water of the river,fish, molluscs and sediments, when the liquid releases take place in rivers. The
sampling is the same for all releases at sea with an additional sampling of shellfish andgastropod molluscs.
The species to be selected for sampling are representative for the environment and thetransfer pathways to Man. The abundance and the mobility of the species are obviously
a criterion of selection, the economic value of the products is also to be considered(lobsters,…). Not to forget that, algae are largely used in the cosmetic industry and thefood industry. They also have the characteristic to accumulate the radionuclides withthe course of time. Therefore, their activity is periodically measured.
Measurements and sampling of the water are related at the same time to the dissolved
forms and the specific forms of radionuclides.
6.3.

Location of the measurement points

In the scope of a normal monitoring procedure, the measurement and sampling points
are located as close as possible to the identified reference groups or to the places
where they exert their activities (fields, vegetable gardens, meadows,…). It is alsostrongly recommended to plan sampling at atmospheric concentration points and points
with a maximum deposit.
 Ambient gamma radiation
The continuous recording of ambient the gamma radiation is normally done from fourmeasuring sites established close to the site, one is placed under the dominant winds
compared to the installation in order to monitor the zone likely to be more affected by
the gaseous effluent releases of the installation. This type of measurement does not
specify the released radionuclides and must considered as a provider of useful
information for a possible alarm.

The level of sensitivity of the system is adapted to local conditions, in particular withpossible fluctuations of the activity levels natural radionuclides like radon.
In addition to the installation of a station under the dominant winds, it is also
recommended to plan stations closer to the most significant deposits ( the mostsignificant deposits are very often located in areas not under the influence of dominantwinds but under winds bringing regular rainfall, this will consequently wash down theplume.
Moreover, uninterrupted recording of ambient gamma radiation at a certain distancefrom the site should be carried out in points to be specified according to local conditionsof urbanization, industrial zones and agricultural zones. In the case of a dispersed
habitat, the points are selected based on the weather condition (direction of the winds).
 Atmospheric aerosols
In order to identify the radionuclides present in the environment and, if necessary, tohelp with the interpretation of measurements of gamma radiation, sampling equipment
for atmospheric aerosols allowing a permanent collection of the radionuclides present in
the air in order to carry out a thorough analysis in a laboratory is installed at the same
stations already mentioned above. For gas iodine, specific filters (cartridges of activatedcarbon) are added downstream from the air stream of the filter system of the sampling
equipment for aerosols. this will provide important information concerning the activity of
the air inhaled by Man, the air intake of the sampling systems are installed at least 1 or
1,5 meters of the ground, at a sufficiently remote distance from any obstacle that might
disturb the airflow.
 Water coming from rain or snowfall
The collection of rain water is carried out at the same stations as the collection of
atmospheric aerosols. The measurement of volumes of the rainfall makes it possible toshow the results in volumic activity and knowing the surface of collection of thepluviometer permits to determine the surface deposits. Determination of gamma
emitting radionuclides is carried out, after filtration of water, by a direct measurement orby a measurement after concentration by evaporation if necessary. Aliquot of thesampling is used to determine the tritium level by direct measurement by liquid
scintillation.
 Deposits of radionuclides on the groundThe sampling locations are selected according to the wind roses by dry weather and by
rainy weather; the distance from the releasing installation must correspond to a
maximum deposit.
Two types of ground are selected for sampling: the ground of a meadow, which is in
general only slightly altered and cultivated ground regularly ploughed. Cultivated groundis ground with a vegetable culture such as the market-gardening grounds, vines,
orchards or cereals.
The ground selected for sampling should if possible be those where the plants growand where agricultural products are taken within the framework of a normal monitoringprocedure (see below). All samples should preferably be taken at the same time.
 Plants and milk

To follow the transfer pathways of the food chains due to releases of a nuclear
installation, sampling of plants (grass, moss, etc) is carried out in stations placed under
the dominant winds of the installation, preferably in the meadows being used to feed theanimals whose milk is also subject of sampling.
In addition, samples are taken from ground and grass of meadows that not only feed
the animals but are also used for forage.
Milk is directly collected from producers whose extensive livestock are grazing or fed forat least two months with fodder coming from the same meadows from where the othersamples have been taken.
 Agricultural products (except milk)
The selection of samples is guided by the most significant local products in terms of
produced quantities and their capacity to accumulate radionuclides. In the scope of afollow-up of releases into the atmosphere, the samples of vegetable-leaves or fruit are
the most appropriate. They are carried out on cultivations in the open field and not in agreenhouse, preferably on vegetables or fruit fully grown.
 Volumic activities in the mixing of the liquid effluents
Measurements of volumic activity are carried out in a fixed place representative for the
mixing zone of the effluents, starting from samples of a semi-release or an
uninterrupted release into the receiving environment. The results are therefore specificvalues (samples of semi-release) representative of the volumic activity reached in thereceiving environment or of the values integrated over the duration of the rejection(regular sampling).
The use of automatic sampling equipment is to be recommended. The volume of watertaken for sampling is specified according to the analysis to be carried out. Concerning ariver, the sampling station is located at a zone were with an excellent mixture of thereleased effluent takes place. The definition of such a zone must be carefully studied bytaking into account the river flow and the distance from the outlet of installation
concerned because it will vary the mixture. Initially, this distance is assessed for thecharacteristic flow rate values (rising, low water level and medium flow). To determine
the specific impact on the installation considered, it is useful to have another station
upstream close to the outlet.
In the marine aquatic field, the sampling stations are defined starting from dipersion
studies of the effluents. Sampling points of sea water permitting to determine the levelsof volumic activity related to the releases are generally located at 500 meters of thereleasing installation. The precise location of the sampling points is always decided
after a radioecologic study and after modelling. A fixed point systematically affected by
the effluents and easily accessible (generally at the coast) is defined; another sampling
point considered as a point of maximum volumic activity at a distance selected (notlocated in the axis of the plume) is also defined; the hour of sampling compared to thetide is specified.
 Aquatic sediments, fauna and flora in the receiving environment
The interministerial decree of November 26, 1999 stipulates the monitoring, by regularinspection visits, of radioactivity in aquatic sediments, fauna and flora in the receiving

environment. The sediments initially play a significant part in the integration ofradionuclides present in the water, in particular those in the form of a particle.
Monitoring of the sediments permits to follow the accumulation of the radionuclides. It istherefore important to monitor the zones of accumulation of fine sediments likely toconcentrate the radionuclides. The choice of the location of the sampling points isbased on the knowledge of sedimentary deposits which are indexed.
When a sampling site comprises sediments of various granulometry (for example
beaches), combined samples are carried out; resulting in an homogeneous mixture, in
identical proportions, of representative samples or fractions of samples in order toapproach the average value of the volumic activities for one radionuclide or overallvalue for the site sampling.
The monitoring of the radioactivity in fauna and flora must preferably relate to all
biological species accumulating the radionuclides (biological indicators) or to all species
used for human consumption. To monitor if the installations operate normally researchon species that are bio-indicators or of the type sentinel are required (because of theircapacity to accumulate the radionuclides quickly). For the flora, they are hydrophytes
fixed or floating, primarily of watery moss and algae. For the fauna, samples are takenfrom the molluscs filterers, like various species of mussels. When a site or a zone isdeprived of such species due to the direct impact of the releases, re-establishment of
the species might be carried out.
In order exclude the effect of variable accumulation of the radionuclides (variations
according to species, according to individuals) due to the composition of the samples
and to establish chronological series easy to interpret, a sample consists of several
individuals of the same species and the same size, therefore roughly of the same age.
To monitor species used for human consumption, generally fish, the same precautions
are taken as for the samples mentioned above.
For the releases at sea, a specific species of alga and mollusc always present on thebeach are taken on both sides of the outlet in at least two sampling stations, as well as
sediments of beaches close to the foreshore.
 Ground water and surface water other than those of the receiving
environment
The monitoring of ground water and surface water other than those of the receiving
environment is meant as a preventive mesure, because normally they should notcontain any form of radionuclides coming from the installation concerned. In addition by
the presence of radionuclides in a water resource intended for human consumption, themonitoring has also a dosimetric vocation.
Water samples are taken from the groundwater directly by drillings or in pedometers byusing pumps. Anyway it is advisable to privilege existing drillings so that the sampling
begins only after the draining of the operating system; To be sure that thecharacteristics of the water collected (pH, temperature, conductivity) are definitely
those of the groundwater.
Concerning irrigation water coming from drillings of the ground water or coming from ariver or channel, the sampling is directly carried out in the distribution system at the sitewhere the water is taken for irrigation. There again, a draining of the system of

distribution is carried out preliminary, so that the characteristics of the water collected
are stable and representative.
This monitoring is supplemented by regular measurements (for example monthly) of theradio activity of drinking water, in points where this water comes from like groundwateror river water affected by liquid effluent releases or even affected by deposits on the
ground of radionuclides coming from gaseous effluents (case of tritium).
6.4.

Frequency of sampling and measurements

Normal measurements procedures, when they are not carried out uninterrupted, haveto be carried out with a frequency corresponding with the periodicity of the releases.
Therefore, all sampling equipment for atmospheric aerosols present near the
installation are continuously in operation to allow at least a daily analysis of the filters ina laboratory in order to determine the volumic activity of gamma transmitting
radionuclides , like the isotopes of cesium and cobalt, and possibly of iodine if they arein the form of aerosols. Moreover, these daily filters, collected over one week or amonth, can be gathered to take weekly or monthly samples because the results of theanalysis may lead to lowering the limits of detection for the gamma transmitters or tocarry out analyzes by alpha spectrometry to determine the volumic activities of thealpha transmitters (in particular plutonium and americium). In addition, periodical
sampling of aerosols at longer distance from the installation should take place weekly.
The monitoring of radionuclide deposits on the ground is at least annual. The sampling
date of the surface layer of the ground is given according to the local meteorologicalcycle: Sampling is carried out at the end of the wettest season.
Sampling on grass and milk is at least monthly.
The frequency of sampling for the monitoring of all agricultural products is normallyannual; the sampling carried out during the season of cultivating: vegetables and fruits
in springtime (salads, strawberries, cherries), in the summer (tomatoes, zucchinis,fishing) and in the autumn (grapes, apples, cabbages).