ML20128H294

Forwards Summary of Foreign Travel to IAEA in Vienna,Au on 960826-30 & from Iaia

ML20128H294
Person / Time
Issue date:	10/07/1996
From:	Clint Jones NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20128H299	List: ML20128H294
References
NUDOCS 9610090301
Download: ML20128H294 (40)

Text

e .

MEMOR ANDUM TO: Carl J. Paperiello, Director i

Office of Nuclerr Mitzrill Safsty

.. . and Safeguards THRU: Donald A. Cool, Director Division of Industrial and Medical Nuclear Safety, NMSS FROM: Cynthia G. Jones, Senior Level Advisor for Health Physics Division of Industrial and Medical Nuclear Safety, NMSS I

SUBJECT:

FOREIGN TRAVEL TRIP REPORT Attached please find a summary of my foreign travel to the IAEA in Vienna, Austria, from August 26-30,1996, in which I was selected as one of two intemational scientific consultants to develop and prepare a Safety Series guide on " Source and Environmental Monitoring for Radiation Protection of the Public" (see Attachment 1).

The Division of Radiation and Waste Safety within the Department of Nuclear Safety at the IAEA has an aggressive schedule for finalizing some of the more important implementation l documents, some of which I have been directly involved in as their Advisory Group Chairperson. Specifically, the IAEA wishes to clarify the regulatory nature of some of documents (such as Safety Series 77, and the above-referenced document which I prepared with Dr. Krishnamony, from the Bhabha Atomic Research Centre, India) to directly refer to the requirements of the IAEA Basic Safety Standards. I believe that this document is particularly of interest to us at the NRC and extremely timely, especially with advent of increasing concems about environmental safety and the potential for members of the public to be exposed from radioactive emissions from our licensed facilities.

The final draft of Attachment 1 is currently undergoing lAEA editorial and technical review. It is anticipated that the final draft will be completed in late October 1996, and then sent to the Advisory Group participants shortly thereafter. The Advisory Group Meeting is scheduled the week of December 2-6,1996 at the IAEA, and I have been requested by the Department of Nuclear Safety to chair this intemational meeting (see Attachment 2). If you have any questions regarding this document, please let me know, and I will arrange a mutually agreeable time for us to meet on this document.

Attachments: As stated cc: J.Greeves, NMSS M.Federline, DWM C E% #e:r L. Ten-Eyke, FCSS D. Morrison, RES d. Nah, Me,(.

J. Shea, IP E. Hemby, IP J. Blaha, EDO g.4.g gx/g Distnbution i IMNS r/f NRC File Center Subject File p%44c DF03 /

OFC IMNSI k gp NAME Chej OM~ /

l DATE 10/$/96

[g:\iaea896.cgj] l 70

' m' - p S_u1 E A 090010 'l 9610090301 961007 PDR ORG NOMA PDR

MEETING TITLE: Scientific consultants meeting for the preparation and finalization of a draft guide on " Source and Environmental Monitoring for Radiation Protection of the Public."

ORGANIZED BY: The Intemational Atomic Energy Agency (IAEA)

DATES OF TRAVEL: August 26-30,1996 ABSTRACT AND/OR

SUMMARY

OF MEETING RESULTS:

At the request of IAEA's Division of Radiation and Waste Safety, Department of Nuclear Safety, C. Jones, Sr. Level Advisor for Health Physics, Office of Nuclear Material Safety and Safeguards, and S. Krishnamony, Head, Health Physics Division, Bhabha Atomic Research Centre were invited as paid scientific consultants to develop, draft and finalize a guide on

" Source and Environmental Monitoring for Radiation Protection of the Public" which will serve as the revision of Safety Series 41.

Recently lAEA's Division of Radiation and Waste Safety has been charged with transforming several technical documents that have been developed over the past several years on 4

environmental and effluent monitoring in the public domain. These documents existed primarily as TECDOCS or draft technical documents and needed to be transformed into either a primary

" regulatory guide" or finalized as a technical reference. This regulatory guide was developed to  ;

directly refer to those requirements of the IAEA Basic Safety Series 115 regarding concise guidance on their interpretation in practice (as shown in the attached draft in italics), much the l same way as was done for Safety Series 77, " Regulatory Control of Radioactive Discharges into the Environment" last year.

l Dr. Krishnamony and I reviewed Safety Series 77, Safety Series 120, " Radiation Protection and the Safety of Radiation Sources," along with a draft TECDOC on environmental monitoring and drafted the attached revised Safety Series 41, which we expanded in scope to account for the conceptual change of radiation protection as well as recent developments in instrumental and environmental monitoring. This version of the Guide describes both the principles and practices i of monitoring for radiation of the public under normal exposure scenarios. Of particular interest l are Sections 3, " Objectives of Monitoring," and 4, " Design of Monitoring Programmes," which go into some detail as to when Regulatory Authorities would initiate environmental monitoring (per IAEA Basic Safety Series 115) for cases involving single-source, multiple-source, or for widespread environmental monitoring.

l ATTACHMENT 1

1996-08 30 SOURCE AND ENVIRONMENTAL MONITORING FOR RADIATION PROTECTION OF THE PUBLIC Attachment 1

_ _ _ _ _ _ ._ _. _ _ _ . . _ _ . _ . _ . _ _ _ _ . _ = _ _ _ _ _ _ _ .

Draft Document FOREWORD . ,

Radiation monitoring is an essential requirement in the framework of radiation protection. Only monitoring can provide actual data on radioactive concentrations in l

ef0uents and in the environment, and on dose rates. It can also be used to demonstrate compliance with authorized limits and provide data to aid optimization of radiation protection. Detailed guidance on monitoring related to radiation protection of the public  ;

last published by the IAEA in 1975 as Safety Series No. 41 entitled " Objectives and D of Environmental Monitoring Programmes for Radioactive Contaminants." Much of that However, it deals with environmental monitoring relevant only to advice is still valid.

releases of radionuclides from nuclear installations.

The public is exposed to radiation from many other sources, some of which are more signi0 cant. The International Commission on Radiological Protection (ICRP) issued i

its Publication 39 " Principles for Limiting Exposure of the Public to Natural Sources of l Radiation" in 1984 for developing its guidance on natural radiation in 1985, the ICRP published guidance on, " Principles of Monitoring for the Radiation Protection of the Population" as Publication 43 and in 1991 published the "1990 Recommendations of International commission on Radiological Protection as Publication 60. On the basis of the 1990 recommendations of the ICRP, the new International Basic Safety Standards for Protection Against lonizing Radiation andfor the Safety of Radiatic:: Sc:arces was finalized in 1996 and wasjointly sponsored by the following organizations: The Food and Agricultura Organization of the United Nations (FAO), the International Atomic Energy Agency (IA the International Labour Organization (ILO), the Nuclear Energy Agency of the Organization for Labour Organization (OECD/NEA), the Pan American Health Organization (PAHO) an, the World Health Organization (WHO). As part of the RADWASS program, IAEA has also published a document on the " Principles of Radioactive Waste Management," whic useful in the development of this Guide. i As a result of these developments, this Guide is the revision of Safety Series No. 41 and ha been expanded to its scope to account for the conceptual change of radiation protect well as relevant developments in instruments and methodology. 'the present Guide describ both the principles and the practice of monitoring for radiation protection of the public u

Source and Environmental Monitoring for Radiation Protection of the Pubhc

-m- 1996-08 30. 2:19pm CONTENTS

..... I

1. INTRODUCTION .. .. ... ... ..... . ......

2

1.1 BACKGROUND

2 1.2 OBJECTIVES . . ... ..............................

3 1.3 SCOPE...........................................

5 1.4 STRUCTURE.. ....................................

6

2. BASIC REQUIREMENTS FOR RADIATION PROTECTION OF THE PUBLIC .9.

2.1 IDENTIFIC ATION OF SOURCES . . . . . . . . . . . . . . . . . . . . . . . . . .

9 2.2 CONTRO L O F EX POS U RE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

9 2.3 RESPONSIBILITY FOR MONITORING . . . . . . . . . . . . . . . . . . . . . .

........................... I1

3. OBJECTIVES OF MONITORING .. 11 GENERAL OBJECTIVES ............ ........... ......

3.1 3.2 SOURCE MONITORING

................... 13 3.3 ENVIRONMENTAL MONITORING ..... 13 3.3.1 Single-source environmental monitoring . . . . . . . . . . . . . . . .

13 3.3.2 Multiple-source environmental m'onitoring ..............

13 3.3.3 Widespread environmental monitoring ................

13 3.4 INDIVIDUAL MONITORING ............................

16

4. DESIGN OF MONITORING PROGRAMMES . . . . . . . . . . . . . . . . . . . . . . . ,

4.1 RELATIONSHIP BETWEEN SOURCE AND ENVIRONMENTAL 16 l MONITORING .................................. 18 '

4.2 SOURCE MONITORING ............................... 22 ENVIRONMENTAL MONITORING ........................

4.3 Critical pathways and groups ........................... l releasing naturally-occurring l Special considerations for facilities radionuclides . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Pre-operadonal studies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l 4.3.1 Single-source environmental monitoring . . . . . . . . . . . . . . . . .

4.3.2 Multiple-source environmental monitoring ...............

4.3.3 Widespread source environmental monitoring .............

4.4 INDIVIDUAL MONITORING .............................

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_ . _ _ . . . . _ . __ _ . _ _ _ _ . . _ .-. . . _ . _ m _ . ._ . . _ _ _ . . . _ _ _ ._ __ . . . _ . .

- i Source and Environmental Monitonng for Radiation Protection of the Public 1996-08 30,2:19pm 1-

1. INTRODUCTION

1.1 BACKGROUND

101. Everyone in the world is exposed to radiation from various sources, natural and artificial. Many reports have been published on the assessment of doses rxeived from these sources [1,2]. Natural radiation usually contributes the largest fraction of the total exposure to humans. Any system of radiological protection must take into account all significant radiation sources. The International Commission on Radiological Protection (ICRP) Report No. 60, as well as the IAEA Basic Safety Standards (BSS) Safety Series No.115 establish basic requirements for protection against the risks associated with exposure to ionizing radiation (hereinafter termed radiation) [3,4). This may include normal and potential exposures to occupational workers, to patients undergoing medical diagnosis or treatment, and to members of the pubic who may receive radiation exposure by a practice or by intervention. These exposures are divided into: occupational exposures which are received at the workplace and result from exposure to radiation or radioactive sources at work; medical exposures which are principally received by patients as a result of medical treatment or diagnosi.i; and public caposures which comprise all other exposures. 1 The public can be exposed to radiation from various sources, both natural and artificial. The BSS establishes basic requirements for radiological protection of the public from both of

\

these sources of exposure and requires that registrants and licensees be responsiblefor the l j

establishment, implementation, and maintenance of appropriate monitoring equipment and surveillance programmes to assess public exposure to the satisfaction of the Regulatory

)

Authority [BSS p. 57/. The IAEA RADWASS document entitled, "'Ihe Principles of 1 i

Radioactive Waste Management" requires that when radioactive substances may be released l

within authorized limits as a legitimate practice into air, water or soil, appropriate safety and control measures should be defined. In addition, adequate records of these surveillance and monitoring fBSS p. 58/ from these programs are also required to be maintained.

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i f

Source and Environmental Monitormg for Radiation Protection of the Public 1996-08 30, 2:19pm 3-i j 106. This Guide describes radiation monitoring for protection of the public in normal  ;

t situations and after accidents for potential long-term exposures. The principles or basic requirements relevant to radiation protection are given in the IAEA Basic Safety Standards.

i i

1 107. Exposure classifications are divided into normal and emergency situations. Normal sitr.tions are covered by this Guide. Emergency monitoring is also important and should l

'oe provided for any major installation as determined by the Regulatory Authority. That i subject, however, is outside the scope of the present Guide. Some aspects of monitoring l

! during emergency situations are described in the IAEA Safety Series No. 86 and 94 for nuclear facilities, No. 91 for medical applications, and No. 87 for transport of radioactive .

l I i materials (6-9].

i 1 Further classification of the normal situation can be divided into public exposure

108.

i j

and occupational exposure. This Guide describes public exposure. Occupational exposure j

is outside the scope of this Guide and is discussed in the IAEA Safety Series No. 84,95 and l 50 SG-D8 [10-12].

i 109. Sources may be defined as physical entities within particular practices (e.g. the release of radioactive effluents from nuclear or industrial installations) that are controllable or as circumstances leading to exposure to the public that may not be controllable (e.g.

exposures from natural radiation). Radiation sources which require or may require monitoring are classified into nuclear facilities, non-nuclear facilities utilizing ionizing radiation, natural sources, fallout from weapons testing, radiation-emitting consumer products, medical applications and transportation of radioactive mataials. This Guide deals with these sources widi the exception of: (1) medical uses of radioactive material or radiation sources in diagnostic or therapy procedures; (2) transportation of radioactive materials and (3) radioactive material disposed of as waste. Because the contribution to the dose to the public from both individual patient discharges (excreta) who have been treated with radioisotopes for medical purposes and transportation of radioactive materials are negligibly small in most situations, they are not covered in this Guide. Monitoring related ;o

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Source and Environinental Morvtonng for Rad stion Protection of the Public 1996 08-30.2:19pm 5

FIGURE 1 SIMPLIFIED MONITORING DIAGRAM r

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^~^--- - -- - _ - __ _

Source and Environtnental Monitoring for Radiation Protection of the Public 1996-08-30. 2:19pm I 7 I i

Sections 5 and 6 discuss modelling and requirements for recording and l monitoring.

l reporting. The final Section 7 delineates quality assurance in the monitoring programme. 1 1

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i 1

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l Source end Enwonmental Monitonng for Radiation Protectson of the Public 1996 08 30,2:19pm

. 9-204. Regulatory authorities should require the management of major controllable s i

to undertake both a defined soerce and environmental monitoring programme outs containing the source.

These programmes are generally designed to assess the level of lI exposure of the critical group from that source. For this purpose, the meas out in the programme should be complemented by the use of specified environme!

biokinetic and dosimetric models.

f 205.

Regulatory authorities should also specify requirements on the condition operation of intermediate and minor sources. The requirements should be i These of exposure resulting from each source and on the total number of such sources.

requirements should include an authorized limit and monitoring procedures.

For minor f j

sources, however, regulatory authorities should normally require only a demonstrati '

a source is being controlled within the dose constraints. Regulatory authorities should l

require routine environmental monitoring programmes for minor sources. For the l of dose from intermediate sources they may require simple programmes and th!

specified models. Only occasional verification of the registrant or licensee data is suggested. (see Section 4, Figure 2 for additional information).  !

206.

In exercising these responsibilities the regulatory authorities should:

ensure that the p'ablic and the environment are protected by establishing and (a) implementing appropriate regulations to enure that the dose limits are no '

and, if necessary, develop their own independent monitoring programmes; (b) identify all sources in the environment that may significantly contribute to exposure of the public; and conversely, identify all sources that may be e or excluded from the requirements for environmental monitoring, l

ensure that the registrant or licensee complies with the appropriate regulations al (c) l regulatory requirements for compliance with the dose constraints and limI wowrrum l

Source and Environrnental Monetonng for Radiation Protechon of the Publ c 11- 1996-08 30, E19pm In e::arcising these responsibilities, registrants and licensecs should:

(a) perform all necessary pre-operational investigations (including, if necessary, pre-operational monitoring) to serve as a basis for effective monitoring programmes; (b) design and provide means for performing adequate source and environmental monitoring programmes during and after operation that will demonstrate that doses to the public satisfy the regulatory requirements and are as low as reasonably achievable.

2.2 IDENTIFICATION OF SOURCES 209. The public may be exposed to a variety of~ radiation sources through a number of different pathways. These sources are classified into natural and artificial. Natural sources  ;

a consist of cosmic rays, cosmogenic radionuclides, and terrestrial radiation sources, such as naturally-occurring "K, "'U and 232Th and their decay products. Medical exposure, fallout from weapons testing, and radiation from nuclear fuel cycle activities belong to artificial ,

I sources. Some of the natural sources as well as most of the artificial sources are controllable and the attributable dose may be reduced. It is necessary to know the level of each exposure from each of the sources and identify their degree of controllability.

l 2.3 CONTROL OF EXPOSURE 210. The exposure of individuals can be limited either by the control of a practice or l l

by intervention. Most of this Guide is concerned with monitoring programmes for practices. l However, some guidance is given on monitoring programmes for situations, such as radon in homes, that may require intervention. In public exposure for practices, the controls should be applied at the source. Only if these cannot be made effective should controls be applied to the environment or to individuals.

wo m i l

3

Sour ce and Environmental Monitonng for Radiation Protection of the Public 1996 08 30,2:19pm 13-214. Once the exposures from all sources are obtained, the contributions from the controllable sources should be estimated to clarify their relative significance.

wonam

Source and Enwronmer tal Morutoring for Radiation Protection of the Public 15- 1996-06 30, 2:19pm (d) the estimation of collective doses; (e) the provision of information to the public additional to that resulting from the primary objectives.

The basic scheme for radiation monitoring for protection of the public is illustrated in Fig. 2.

3.2 SOURCC MONITORING 303. Monitoring for radiation protection of the public can be divided into several categories: source monitoring (which includes source and effluent monitoring); environmental monitoring (which includes single-source, multiple-source and widespread sources environmental monitoring) and in extremely rare cases, individual monitoring for members of the public.

304. The objectives of source monitoring are:

to demonstrate compliance with the authorized and/or operational limits (a) on releases of airborne and liquid radioactive materials; (b) to provide adequate data and information for the estimation of public exposure that results from the operation of the installation; to indicate whether and to what extent environmental monitoring may be (c) required; (d) to provide adequate information to demonstrate that the plant operation and effluent treatment and control system are performing properly; marm m

Source and Environmental Morutonng for Radiation Protection of the Pubbc 1996-08 30, 2.19pm 17 -

3.3 ENVIRONMENTA1 MONITORING 305. The primary objectives of environmental monitoring are to:

l assess actual or potential doses to individual members of the public o (a) members of the critical group from operation of each source; i

l evaluate the adequacy and effectiveness of the containment, and co (b) systems; and i

detect cb ges and evaluate long-term trends in activity concentrations ;o (c) dose rates in the environment.

306.

The environmental monitoring programme may fulfill one or more of the additional supplementary objectives:

confirm predictions based upon source monitoring and models of tra (a) through the environment; (b) provide reassurance that doses based on source monitoring are n seriously in error due to unmonitored releases; discover any new pathways or modes of exposure; (c) i maintain capabilities for rapid evaluation and response to an unusua (d) situation; (e) provide information to the public wherever necessary on activ concentrations in the environment or on collective dose or public exposure; and arm m

Source and Eneronmental Monitonng for Radiation Protection of the Pubhc 19- 1996-08 30, 2:19pm 3.3.3 Widespread environmental monitoring 309. Monitoring programmes may be carried out to assess doses from natural radionuclides, fallout from weapons nuclear testing, or even from consumer products containing radioactive material in order to assess the regional and global components of exposures resulting from releases oflong-lived radionuclides from the nuclear fuel cycle that l are widespread in the environment. l 310. Widespread environmental monitoring programmes may be carried out by the Regulatory Authorities to fulfill one or more of the following objectives: ,

l 1

(a) provide an assessment of the collective dose to the whole population from )

i these sources:

(b) assess levels, detect changes and evaluate long-term trends in the total dose and the relative contributions of each source to the total; (c) assess the need for control of any specific source of exposure (e.g.

Interuntion to reduce radon concentration in homes);

(d) provide information to the public on environmental levels and doses; and j 4

I (e) maintain capabilities for rapid evaluation and response to unusual

)

situations.

3.4 INDIVIDUAL MONITORING 240NffeeMT

Source and Environmental Monstonng for Radiation Protecuon of the Pubhc 1996-08 30,2:19pm 21 -

4. DESIGN OF MONITORING PROGRAMMES 4.1. RELATIONSHIP BETWEEN SOURCE AND ENVIRONMENTAL MONITORING 401. Different types of monitoring programmes may be required according to whether the source emits radiation, whether radionuclides are discharged from a defined location or whether the source is widespread in the environment. The first category includes installations in the nuclear fuel cycle such as uranium mines, mills, enrichment and fuel fabrication plants, nuclear power reactors, spent fuel reprocessing plants, waste storage and disposal sites. It also includes research reactors, research institutes, hospitals and medical research institutes, isotope production and handling facilities and their associated waste management operations. The release to the environment of naturally-occurring radionuclides from the non-nuclear industry could also be included in this category. In the second category, widespread sources include those distributed to the public (consumer products, natural gas and building materials or manufactured goods that may contain higher than average concentrations of radionuclides) as well as natural radiation, fallout from nuclear weapon testing and contamination due to past accidents. Sources which are distributed to the For public represent practices and for these, control may be exercised before distribution.

these latter sources, the same considerations apply in the design of monitoring programmes but the extent of the actual monitoring will be generally much smaller.

402. The scale of the monitoring programme should reflect the significance of the dose to critical groups and to the population from planned releases. For major installations, the routine environmental monitoring programme should be designed to provide a good basis for post-accident monitoring. In the event of an accident, this monitoring programme will need to be modified and expanded. Guidance for monitoring in accident situations are given in the IAEA Safety Series No. 86 and 94 [10,11).

403. Major sources in this first category will require continuous source monitoring and Intermediate sources may require souro:

comprehensive environmental monitoring.

410Nrt en.9trT

Source and Environmental Monitoring for Radiation Protection of the Public 23- 1996-08 30,2:19pm 406. In general, detailed design and operation of source monitoring and environmental monitoring programmes' are treated separately since the dose rates and quantities of j l

radionuclides involved are very different. In may cases, different agencies, as well as individuals are often involved. However, when both types of programme are conducted, there must be good liaison between the two because information obtained from one l programme may influence the conduct of the other. Generally, all programmes should be subject to periodic review to ensure that measurements are relevant for the purpose of the l programme and that no significant routes of discharge or of environmental transfer have been overlooked.

I 4.2 SOURCE MONITORING ,

i Design of source monitoring programmes i

407. Design of the source monitoring programme should be such that it enables verification of compliance with the discharge limits and criteria as specified in the authorization issued by the Regulatory Authority. This may require radionuclide- specific measurements or gross activity measurements as appropriate. Measurements should be carried out at the point where data best represents the material actually released; this will normally be at the point of release.

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_ . . _ = . . . - -. . . - . . .- . . . - . -. . .

Source and Environmental Monitonng for Radiation Protection of the Public a

25 - 1996-08-30,2:19pm 411. Other information that could be included in the monitoring programme are:

a) chemical form of the radio-nuclide released; b) solubility of the radio-nuclide species; 1

1 1

c) particle size distribution in the case of airborne effluents; ,

i

d) pH in the case of liquid effluents; and e) meteorological and hydrological factors.

i i

i Special considerations for facilities releasing naturally-occurring radionuclides i 412. Although the general objectives and design of source-related environmental monitoring programmes also apply to facilities that releases naturally occurring radionuclides, l

there are some special difficulties that merit particular attention. Such facilities include i uranium and thorium mines and mills, and phosphate fertilizer plants. A major difficulty of the environmental monitoring programme is to assess the effect of releases in the presence of natural levels of the same radionuclides.

413. Mining sites are situated in areas of high natural concentrations of these ,

radionuclides and milling facilities are frequently situated nearby. In these areas, the normal i f

concentrations of naturally-occurring radionuclides in environmental media are high and l subject to considerable variation. In such situations, assessments of doses to the public  !

l resulting from these operations is primarily based on source monitoring and modelling.

However, where environmental monitoring is undenaken, registrants or licensees will wish

to distinguish the effect of the releases from normal levels. An adequate pre-operational l programme is then essential to assess normal levels and their variation. The operational MONfT96 RFT

I Source and Enwronmental Monitonng for Radiation Protection of the Pubhc 27- 1996-08-30, 2:19pm (b) Sample collection should be designed to obtain samples which may 1 provide quantitative estimation of the radionuclide releases from the source.

418. Different types of sampling can be used which take into account the operating and release conditions, the design of the release system and equipment, the type of release and the nature of the materials to be measured, etc. Sampling can be continuous, periodic, l

)

special or self-actuated. Continuous sampling is required when there may be wide variation I in the concentration of the radionuclides or in the discharge-rate, or when the likelihood and potential consequences of unplanned releases are not trivial. Periodic sampling may be sufficient when the concentrations of all radionuclides are relatively constant, when unusual va) ations are unlikely and when the predicted doses are low. Periodic sampling may be act aated automatically. The frequency of such sampling should be periodically reconsidered.

Spucial sampling is carried out, whenever necessary, to monitor either special releases ret .iired by operational conditions or unusual occurrences. Self-actuated sampling is aci )mplished by devices which automatically collect samples when rapid variation occurs in the concentration of the radionuclides released. Actuation of such sampling may be automatically linked to devices which provide a direct measurement of the quantities released.

419. Laboratory analyses may be required to supplement in-situ measurement; for some nuclide, they may be the only means of measurement. Gamma-ray emitting radionuclides may be determined by direct measurement with detectors of adequate resolution; natural uranium and thorium may be determined by chemical methods; some radionuclides can be determined only by radiochemical separation followed by appropriate radiometric techniques

[21,22]. The measurement procedures must provide sufficient reliability, accuracy and comparability of the results.

4.3 ENVIRONMENTAL MONITORING S40NTT96MT

Source and Environmental Monitonng for Ra$ation Protection of the Pubhc 1996-08 30. 2:19pm requirement for homogeneity has certain implications for the size of the group. Usually, the group will not consist of a single individual. However, in extreme situations, for example, when considering exposures that may occur far in the future, it may be convenient to define the critical group in terms of a single hypothetical individual. In practice, the critical group size could be relatively small, although in a situation where a population is exposed uniformly, it would be possible to consider the entire population as the critical group. Those aspects of behaviour that are most likely to affect the doses received include proximity to the source, the occupancy time in areas of elevated external dose rates or activity concentratians in air, and the consumption rates of foodstuffs.

423. To select 'hc group that is most highly exposed it is necessary to characterize the distribution of habits in the relevant population. The detail required will depend upon the estimated dose. If this is low, national statistics may be used or reasonably conservative estimates may be based on national statistics. There are some circumstances, however, where there are substantial variations in characteristics and where doses may be such that more detailed analysis is warranted. Surveys provide a sample of the distribution of characteristics at a particular time and it should be recognized that the results of any one particular survey may be subject to fluctuations. The survey data should be used to postulate the underlying distribution and subsequent surveys should be examined to confirm or modify it. Once the underlying distribution is established it is then necessary to select the critical group. To satisfy the homogeneity criterion, it is suggested that the ratio between maximum 1

and minimum estimated doses within a critical group should not exceed an order of j magnitude unless the mean dose approaches the authorized limit; in that case, the range 1

should not exceed a factor of three. Recognition must also be given to the fact that

)

individuals may be members of more than one critical group.

424. In dose calculations, account should be taken of the age and appropriate biokinetic parameters of the critical group and of the different chemical and physical forms of radioactive material in the environment.

40ONrT96 IlfT l

l

source and Enwonmental Monitoring for Radiation Protection of the Pubhc 31 - 1996-08 30, 2:19pm (i) the identification of critical nuclide and critical exposure pathways; (j) the preliminary determination of critical groups; (k) the prediction of doses to population groups and collective doses to the population as a whole.

425. The pre-operational studies should indicate which radionuclides and pathways of exposure are of prime importance, both in relation to critical groups and the population.

These studies may enable derived limits for concentrations in environmental materials to be calculated; derived limits correspond to the dose limits and the regulatory authority may wish to specify investigation levels, set at some fraction of derived limits, above which some specified action or investigation should take place. The pre-operational programme might also identify suitable indicator materials; these are media that do not necessarily form part of the pathway to man and are therefore not used for dose assessments, but are sensitive indicators of trends in environmental levels. The pre-operational programme may a'so serve to train staff and to test the equipment, instruments and organization of the operational programme.

Monitoring Techniques 426. A sampling strategy that includes specification of the type of samples to be taken, sampling locations, frequency sampling, etc. should be adopted by Registrants or licensees that enables the dose to the critical group among the members of the public to be assessed with sufficient accuracy. These samples could come from the atmosphere, aquatic, and terrestrial compartments in the environment. They are chiefly air, water, and foodstuffs.

Extemal radiation exposure from effluent plumes and submersion doses as well as external exposure arising from ground or sediment-deposited activity should also be assessed.

Measurement techniques include gross activity estimates, radionuclide-specific spectrometry woem

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1-f Source and Environmental Morvtonng for Radiation Protection of the Pubhc

33- 1996 08 30,2

19pm

} (d) the significance of any changes in the physio-chemical form of radionuclides; t

(e) frequency of sampling or measurement which may depend on the half life of the

radionuclide. -

4 430. Single-source environmental monitoring programmes should be reviewed l

l periodically. There may be changes in the environment itself or changes in the registrant's or licensee's discharge to the environment; in particular individuals' occupational, j recreational and dietary habits may change. Changes in the habits of critical groups will be 1

revealed by periodic habit surveys but those in charge of environmental monitoring

• a i programmes should be alert to changes in sub-critical pathways as well. Changes in the 1

manner of operation of the installation or in the nature of the discharges should also lead to reassessment of the environmental monitoring programme to ensure its continuing validity. l j An example for the design of an environemtnal monitoring programme for a major source i

l is provided in Fig. 4. Results from the monitoring programme should be critically reviewed j to assess the need for any modification to the programme itself. With experience it should .

! be possible to reduce the scale of the environmental monitoring programme or to stop it completely, but there may be situations that indicate a need for more or different analyses.

l

! One problem that the programme designer must contend with is the increasing public demand .

for reassurance on the topic of environmental contamination with radionuclides. Even if it  ;

is possible to demonstrate scientifically on the basis of source monitoring and modelling that  !

l an e- Jonmental sampling programme is not required, there may still be public pressure to a

. y a limited programme of environmental measurements that the effect of discharges i l

l s small as a matter of public reassurance. i i ,

i

431. For sources that require comprehensive environmental monitoring programmes it o

] is necessary to consider a number of routes of exposure (see Figure 3]. Discharges to the atmosphere may give rise to external doses from the plume or from deposited radionuclides, the radionuclides may be inhaled or they may be transferred through food chains. Integrating  !

dosimeters at suitable locations can adequately assess external dose rates. Doses from l wowrrw.ars 1

I  :

5 .

I Source and Enwronmental Monitonng for Radiation Protection of the Pubhc 1

35- 1996-08 30,2:19pm l

s 4.3.2 Multiple-source environmental monitoring 435. Regulatory authorities may wish to keep under review the level of radionuclides in the environment that may result from a combination of sources. although each does not necessarily require an environmental monitoring programme. Such a situation could occur for example if several hospitals or research institutes may discharge radionuclides into the j same body of water; the regulatory authorities may then wish to monitor water supplies to assess the aggregate effect of all the discharges. However, for proper design of the

monitoring programme, the regulatory authorities would need some information on the radionuclides discharged, their chemical and physical form and the frequency with which a 1 j discharges are made, so that appropriate collection and measurement techniques could be

employed.

)

4.3.3 Widespread environmental monitoring 436. Widespread sources of natural or artificial radioactivity may lead to radiation exposure to members of the public. These types of sources include consumer products or

'\

\ other products distributed to the public, fallout from weapons testing and the regional and global dispersion of long-lived radionuclides released from the nuclear fuel cycle, as well as natural radiation. Since the sources are widespread, it is not possible generally to define critical groups, in the sense used in Section 2. Hence, source and environmental monitorint programmes may need to be developed and implemented by the Regulatory Authority to evaluate changes in the background levels of radiation or radionuclides as a result of regulatory-approved activities.

437. Doses to members of the public from background radiation may come from naturally-occurring radiation from cosmic rays, terrestrial radiation (radon, uranium and thoron), as well as through intakes of radionuclides in diet (i.e., drinking water and food).

In addition, naturally-occurring radionuclides (such as the use of phosphate fertilizers or the 440NTT96MT

Source and Enwon nental Monitonng for Radiation Protection of the Public 37- 1996-08 30. 2:19pm 137 are examples. Doses to members of the public from these sources typically result from euernal irradiation and from internal irradiation through the consumption of foods.

441. The resulting Regulatory Authority environmental programme is generally characterized by wide geographical coverage. The main factors that influence the location of the measuring and sampling points are:

(a) the size of the territory considered; (b) geology, hydrology and other principal geographical features (mountains, coasts, rivers, lakes);

(c) climate (precipitation);

(d) population distribution; and (e) dietary and living habits.

442. For example, the siting of measuring and sampling points depends upon the likely  ;

1 variability of dose rates and activity concentrations with location and on the population distribution. In the case of diet, collection of representative samples of foodstuffs and water l should take account of geographical and seasonal factors to ensure that all important sources 1

are included.

443. For consumer products, Regulatory Authorities may wish to control the distribution. Considerations such as thejustification for using a radioactive source or a device that may give rise to doses to the public are beyond the scope of this report, although regulatory authorities will wish to consider the relative merits of such devices and any non-radioactive alternatives. Additional guidance may be found in Refs. [29, 30].

440NTT96 RPT

Sovce and Environmental Monitonng for Radiation Protection of the Pubhc 39- 1996-08 30, 2:19pm

5. DOSE ASSESSMENT 5.1 MODELLING 501. The use of models is required to convert the information from monitoring programmes into an assessment of dose to members of the public. When environmentally dispersed radionuclides are ingested or inhaled, models are required to describe and quantify environmental transfer processes as well as the biokinetics of the radionuclides in the human body and the associated dosimetry.

502. Where the doses are expected to be well below dose constraints, it is adequate to make an estimate based on simple models and conservative assumptions. When doses may exceed a small fraction of authorized levels, more refined models and realistic parameters are required. In general, the closer to man that the measurements are made, the simpler the model required.

503. Assessment of doses from a particular source is dependent upon models representing the pathways between the source and the exposed individuals. Where environmental monitoring permits the impact of that particular source to be evaluated, the dose assessments may be supplemented by environmental measurements. For comparison with constraints, models should relate to real or postulated critical groups.

504. Environmental measurements generally provide information on activity concentrations in environmental media that may result from a number of sources and thus these measurements may be used for an individual-related dose assessment.

5.1.1. Specific activity models 505. The specific activity methodology for calculating dose assumes that an equilibrium ratio exists between the radioactive and stable isotopes in the environment and in the human elONITt6 RFT

Source and Environmental Monitonng for Radiation Prctection of the Pubhc 41- 1996-08-30, 2:19pm workers based on Reference Man and dosimetric models, but only provisional guidance is given on calculating the values of committed effective dose per unit intake for the public.

Account should be taken of any differences from Reference Man in respect of sex, age, organ size and metabolic parameters if the calculated or estimated committed effective dose per unit intake approaches the constraint or dose limit. Allowance may also be made for the physical and chemical form in which the radionuclides are present in the environment. ICRP is currently preparing guidance on age-dependent doses to members of the public from intake of radionuclides, and partly published in ICRP Publication 56 [37] for a limited number of radionuclides.

5.1.5. Determination of environmental models 509. The simplest model that provides a sufficiently accurate estimate of the parameter to be evaluated should be chosen. Safety Series No. 77 provides additional information on the application of these models for limiting dose [6]. The quantities ultimately required from monitoring and modelling are doses and committed doses from specified sources to members of critical groups or the corresponding collective quantities for larger population groups. In addition, models are described by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) [1], by the ICRP [38], and by the IAEA [23]. .

)

l 510. All models are to some degree based upon observations; the parameters used in i them should be verified experimentally if validity for a given purpose is claimed. When models are used entirely or in part to estimate doses from practices some verification by the regulatory authority should be attempted before the practice is introduced. When the practice has commenced, the monitoring programme may be implemented to achieve further verification. A less complex programme is sufficient when verification is satisfactory.

l 440Nff96 APT i

l Source and Enwonmental Monitonng for Radiation Protection of the Pubhc 43- 1996-08 30, 2:19pm

6. RECORDING AND REPORTING OF RESULTS 601. The recording and reporting of measurement results and related information should l

satisfy the objectives of the monitoring programme. These objectives may require calculation of critical group and collective doses or merely a comparison of measured values with appropriate derived levels.

6.1 RECORDING AND REPORTING OF SOURCE AND ENVIRONMENTAL MONITORING RESULTS 602.

In accordance with the BSS, registrants andlicensees, during the operationalstages ofsources under their responsibility, shall:

(a) record the monitoring results and estimates exposures; (b) report the monitoring results to the regulatory authority at approved inten>als; and (c) repon promptly to the regulatory authority any discharges exceeding the authorized discharge limits in accordance with reporting criteria established by the regulatory authority [p. 61J.

603. The main purpose of recording source monitoring data is to permit an estimate of external dose rates or quantities of radionuclides released. Source monitoring data must be presented in terms which can be directly compared with the prescribed limits. In general, for airborne and liquid discharges, this will be the total activity of each radionuclide released by each route during the reporting period. If activities are expressed in terms of gross beta or gross alpha, an indication of typical radionuclide composition should be given. However, this type of reporting should be avoided as far as possible because of the inherent uncertainties in the interpretation of the rewIts. Alternatively they can be expressed in terms of the most restrictive radionuclide that might be present in the mixture.

SiONfi96MT

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i Source and Environmental Monitonng for Radiation Protvetion of the Public j j

b 1996 08 30,2:19pm

i l

7. QUALITY ASSURANCE i

I Quality assurance may be describe as comprising those planned and systematic 701.

actions that are necessary to provide adequate confidence in the results of a monitoring l' i programme. All monitoring programmes must be subject to adequate quality assurance I

arrangements. Quality assurance is an essential aspect of " good management". Good i

]

management contributes to the achievement of quality through thorough analysis of the tasks

! to be performed, identification of the skills required, the selection and training of appropriate l personnel, the use of appropriate equipment, the creation of a satisfactory environment in- l

} which activity can be performed and a recognition of the responsibility of the individual who is to perform the task. Briefly stated, then, a quality assurance programme should provide  !

I for a disciplined approach to all activities affecting quality, including, where appropriate,

! verification that each task has been satisfactorily performed and that necessary corrective ,

a '

4 actions have been implemented. It must provide for production of documentary evidence to

demonstrate that the required quality has been achieved. However, quality assurance can be costly; the effort devoted to quality assurance for a particular measurement procedure should

! be commensurate with the importance of that measurement within the monitoring programme.

i j ,

l 702. An adequate quality assurance programme must be designed to ensure that:

t i

U) forpurposes ofmonitoring and wnfcation ofcompliance, suitable equipment shall _

1 .

be provided and unpcation procedures introduced, documented and implemented i l (BSS p. 27];  !

, (b) equipment and instruments shall be properly maintained and periodically tested to i t

ensure that they function correctly [BSS p. 27];

a  :

4

_m.m ,

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e Source and Environmental Monitonng for Radiation Protection of the Public 47 - 1996 08-30, 2:19pm (f) Measurement results should be presented in a uniform manner. Uncertainties due to the random nature of radioactive decay should be calculated and expressed in a uniform way. Other uncertainties should be quantified where possible; (g) Staff should be well-trained and motivated.

704. The quality of results should be demonstrated by:

(a) a programme of measurement of suitable blank and reference samples; (b) the inclusion of replicate samples in the measurement programme; (c) inter-laboratory comparison of methods and instruments on national or international base.

l

)

WONff96.kFT

Source and Envronmental Monitonng for Radiation Protection of the Pubhc 49 - 1996-08-29. 4 57pm REFERENCES

[1] UNITED NATIONS SCIENTIFIC COMMITTEE ON THE EFFECTS OF ATOMIC RADIATION, Sources Effects and Risks oflonizing Radiation, United Nations, New York (1988).

[2] INTERNATIONAL COMMISSION ON RADIATION PROTECTION, Principles for Limiting Exposure of the Public to Natural Sources of Radiation, Publication l 39, Pergamon Press, Oxford and New York (1984).

[] INTERNATIONAL COMMISSION ON RADIATION PROTECTION,1990 Recommendation of the International Commission on Radiological Protection, Publication 60, Pergamon Press, Oxford and New York (1991).

[] INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for Radiation Protection,1996 Edition, Safety Series No. I15, IAEA, Vienna (1996).

[] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Material, Safety Series No. 6, IAEA, Vienna (1985).

[6] INTERNATIONAL ATOMIC ENERGY AGENCY, Techniques and Decision Making in the Assessment of Off-site Consequences of an Accident in a Nuclear Facility, Safety Series No. 86, IAEA, Vienna (1987).

I

[7] INTERNATIONAL ATOMIC ENERGY AGENCY, Response to a Radioactive Materials Release Having a Transboundary Impact, Safety Series No. 94, IAEA, Vienna (1989).

[8] INTERNATIONAL ATOMIC ENERGY AGENCY, Emergency Planning and (

Preparedness for Accidents Involving Radioactive Materials Used in Medicine, l Industry, Research and Teaching, Safety Series No. 91, IAEA, Vienna (1989).

[9] INTERNATIONAL ATOMIC ENERGY AGENCY, Emergency Response Planning l and Preparedness for Transport Accidents Involving Radioactive Materials, Safety ,

Series No. 87, IAEA, Vienna (1988). l

[10] INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Principles for Occupational Radiation Monitoring, Safety Series No. 84, IAEA, Vienna (1987).

[11] INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Monitoring in the Mining and Milling of Radioactive Ores, Safety Series No. 95, IAEA, Vienna (1989).

S60Ntrw stPT

o. }

I . ,

4 i

3 Source and Ennonmental Monnonng for Radeten Protection of the Pubic i

. 1996-08-29. 4 57pm I

Routine Releases. Exposure of Critical Groups, Safety Series No.- 57, IAEA, 4

Vienna (1982).

[24] INTERNATIONAL ATOMIC ENERGY AGENCY, Measurement of Radionuclides j in Food and the Environment, A Guidebook, Technical Reports Series No. 295, 1 IAEA, Vienna (1989).

I

[25] INTERNATIONAL ATOMIC ENERGY AGENCY, Methods of Surveying and Monitoring Marine Radioactivity, Safety Series No.11, IAEA, Vienna, (1965).

I i [26] INTERNATIONAL COMMISSION ON RADIATION UNITS AND l hEASUREMENTS, Determination of Dose Equivalents Resulting from External j Radiation Sources, Report 39, ICRU, Bethesda, MD (1985).

l [27] INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, i Reference. Man: Anatomical, Physiological and Metabolic Characteristics, j  ; Publication 23, Pergamon Press, Oxford and New York (1976).

j-j [28) NUCLEAR ENERGY AGENCY OF THE OECD, A guide for Controlling Consumer Products Containing Radioactive Substances, OECD/NEA, Paris (1985).

l [29] NATIONAL COUNCIL ON RADIATION PROTECTION AND l MEASUREMENTS, Radiation Exposure of the U.S. Population from Consumer

Products and Miscellaneous Sources, Report No. 95, NCRP, Bethesda, MD (1987).

1 j [30]

i j [31] KATHREN, R.L., The United States Transuranium and Uranium Registries:

i Overview and Recent Progress, Radiation Protection Dosimetry, 26, pp. 323-330 (1989).

{

l [32] from Dr. F. FRY l

! [33] INTERNATIONAL ATOMIC ENERGY AGENCY, The Radiological Impact of Radionuclides Dispersed on a Regional and Global Scale: Methods for Assessment i and Their Application, Technical Reports Series No.250, IAEA, Vienna (1985).

[34] INTERNATIONAL' ATOMIC ENERGY AGENCY, Atmospheric Dispersion in

} Nuclear Power PI .nt Siting, Safety Series No. 50-SG-S3, IAEA, Vienna (1980).

j i

a Stowrite kr7 4

o Source and Envr mental Monctonng for Rad 6abon Protecten of the Pubhc l

[

19%C8-29. 4 57pm 53 f BIBLIOGRAPHY j i

1. DOSE ASSESSMENT COMMISSION OF THE EUROPEAN COMMUNITIES, RADIATION l PROTECTION, The Impact of Conventional and Nuclear Industries on the i

Population: A Comparative Study of the Radioactive and Chemical Aspects, CEC .

Report EUR 10557 EN (1988). l

.t NATIONAL COUNCIL ON RADIATION PROTECTION AND l' MEASUREMENTS, Radiological Assessment: Predicting the Transpon, Bioaccumulation, and Uptake by Man of Pdionuclides Released to the r Environment, Report No. 76, NCRP, Bethesda, MD (1984).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Public Radiation Exposure from Nuclear Power Generation  !

in the United States, Report No. 92, NCRP, Bethesda, MD (1987).  ;

~

NATIONAL RADIOLOGICAL PROTECTION BOARD / COMMISSARIAT A i L'ENERGIE ATOMlQUE, Methodology for Evaluating the Radiological Consequences of Radioactive Effluents Released in Normal Operations, Joint Rep. i No. V/3865/79e, Commission of the European Communities, Luxembourg (1979). [

UNITED NATIONS SCIENTIFIC COMMITTEE ON THE EFFECTS OF  ;

ATOMIC RADIATION, Sources, Effects and Risks of Ionizing Radiation, UN, i New York (1988). 1

2. SOURCE MONITORING ,

4 I

INTERNATIONAL ATOMIC ENERGY AGENCY, Monitoring of Airborne and i

Liquid Radioactive Releases from Nuclear Facilities to the Environment, Safety Series No. 46, IAEA, Vienna (1978).  ;

)

Monitoring of Radioactive Effluents from Nuclear Facilities (Proc. Int. Symp.

Portoroz,1977), IAEA, Vienna (1978).

i UNITED STATES NUCLEAR REGULATORY COMMISSION, Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous .

Effluents from Nuclear Fuel Processing and Fabrication Plants and Uranium Hexafluoride Production Plants, US Regulatory Guide 4.16, Rev.1, Washington ,

D.C. (1986). l wounw m  ;

. - . . . _ . _ . _ _ _ . . -. . _ . _ . _ _ ,_~--m__..__ _ . _ . __ __ _ _.__

l c

d 4 Source and Environnwntal Mondonng for Radetion Protection of the Public

55 - 199G08-29. 4 57pm l NATIONAL COUNCIL ON RADIATION PROTECTION AND

! MEASUREMENTS, lodine-129: Evaluation of Release from Nuclear Power i Generating, Report No. 75, NCRP, Bethesda, MD (1983).-

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREhENTS, Exposures from the Uranium Series with Emphasis on Radon and its Daughters, Report No. 77, NCRP, Bethesda, MD (1984).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Evaluation of Occupational and Environmental Exposures to Radon and Radon Daughters in the United States, Report No. 78, NCRP, Bethesda, MD (1984).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Carbon-14 in the Environment, Report No. 81, NCRP, Bethesda, MD (1985).

SUhERLING, T.J., The Use of Mosses as Indicators of Airborne Radionuclides, Sci. Total Environ., 35 (1984) 251.

TSCHURLOVITS, M. BENINSON, D., Statistical Characterisation of a Critical Group, Radiat. Prot. Dosim., 4 (1983) 33.

UNITED STATES ENVIRONMENTAL PROTECTION AGENCY, Environmental Radioactivity Surveillance Guide, ORP/SLD-72-2, EPA, Washington, D.C. (1972).

UNITED STATES NUCLEAR REGULATORY COMMISSION, Programmes for Monitoring Radioactivity in the Environs of Nuclear Power Plants, US Regulatory Guide 4.1, Washington D.C. (1975).

UNITED STATES NUCLEAR REGULATORY COMMISSION, Environmental Technical Specifications for Nuclear Power Plants (for comment), US Regulatory Guide 4.8, Washington D.C. (1975).

4. DOSE RATE MEASUREMENTS COMMISSION OF THE EUROPEAN COMMUNITIES, Radiation Protection - 48, Intercomparison of Environmental Gamma Dose Rate Meters, A Comprehensive Study of Calibration Methods and Field Measurements, Part II,1987 to 1989 Experiments, CEC Report EUR 12731 EN (1990).

sam m

. . . . .~ ~ . - _ . _ - . _ - - _ . - . . - . - . . .. . -.

J d

\

Source and Envronrnental Monitonng for Rad 6ation Protectson of the Pubhc 57 1996-08 29, d $7prn l

INTERNATIONAL ATOMIC ENERGY AGENCY. Reference Methods for Marine

Radioactivity Studies. Technical Repon Series No. I18, IAEA, Vienna (1970).

INTERNATIONAL ATOMIC ENERGY AGENCY, Measurement of Radionuclides in Food and the Environment, A Guidebook, Technical Repon Series No. 295, IAEA, Vienna (1989). ,

INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Monitoring in the I Mining and Milling of Radioactive Ores, Safety Series No.95, IAEA, Vienna (1989).

l INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, General Principles for Sampling Airborne Radioactive Materials, ISO 2889-1975(E),

Geneva, Switzerland (1975).

INTERSOCIETY COMMITTEE FOR A MANUAL OF METHODS FOR AMBIENT AIR SAMPLING AND ANALYSIS, Methods of Air Sampling and Analysis, American Public Health Assoc., Washington D.C. (1972).

LANGER, G.H., Jr., PACER, J.C., JOHNSON, V.G., GILLINGS, M.A.,

Evaluation of Methods for the Estimation ofIndoor Radon Daughter Concentrations for Remedial Action Programmes, GJfrMC-04, Bendix Field Engineering Corp.,

Grand Junction, Colorado (1982).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Tritium Measurement Techniques, Report No. 47, NCRP, i Washington, D.C. (1976). )

i NATIONAL COUNCIL ON RADIATION PROTECTION AND  !

MEASUREMENTS, Environmental Radiation Measurements, Repon No. 50, j NCRP, Washington, D.C. (1976).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Instrumentation and Monitoring Methods for Radiation Protection, Report No. 57, NCRP, Washington D.C. (1978).

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, A Handbook of Radioactivity Measurements Procedures,2nd Edition Report No. 58, NCRP, Bethesda, MD (1985) ,

NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, Measurement of Radon and Radon Daughters in Air, Report No. 97, NCRP, Bethesda, MD (1988).

l l

wounu m 1

_ _ . _ _ . _ . _ . _ _ _ _ . _ _ _ _ _ . - ~ _ - _ _ _ _._. _ . _ . . _ .. .

l i* i Source and Erivironrnental Monnonng for Radiation Protection of the Public l 59 - 1996-06-29. 4 57pm t j-  :

t 3

SUMERLING, T.J., Calculating a Decision Level for use in Radioactivity Counting i

! Experiments, Nucl. Instrum. Methods Phys. Res., 206 (1983) 501.

TITLE, C.W., How to Apply Statistics to Nuclear Measurements, Nucl. Chicago i  !

Tech. Bull. No. 14 (1962). l

i i  !

7. QUALITY ASSURANCE j i l

. DUX, J.P., Quality Assurance in the Analytical Laboratory, Am. Lab., 15 (1983) l

54.  !

I HARLEY, J.it, VOLC110K, ii.L., BOWEN, V.T., " Quality Control m  ;

Radiolochemical Analysis", Reference Methods foi Marine Radioactivity Studies )

11, Technical Report Series No.169, IAEA, Vienna t1975) 63.  ;

I HUNT, D.T.E., DEWEY, D.J., The Use of Cumulative Sum Charts (Cusum Charts) j in Analytical Quality Control, Medmenham Lab., Water Res. Cent. Environ.

Protection, UK, Tech. Rep. TR 174 (1982). ,

INTERNATIONAL ATOMIC ENERGY AGENCY, Quality Assurance Records System, A Safety Guide, Safety Series No. 50-SG-QA2, IAEA, Vienna (1979).

UNITED STATES NUCLEAR REGULATORY COMMISSION, Quality Assurance for Radiological Monitoring Programmes (Normal Operations) - Effluent Streams and the Environment, US Regulatory Guide 4.15, Rev.1, Washington D.C.

(1979).

e S,0Nff96 ftFT

e Source and Enwonmental Monttonng for Rad:ston Protecten of the Pubhc 61 - 1996-08-29 4 57pm CONTRIBUTORS TO DRAFTING AND REVIEW Ahmed, J.U. International Atomic Energy Agency, Austria Asculai, E. International Atomic Energy Agency, Austria Boeri, G.C. Comitato Nazionale per la Ricerca e per lo Sviluppo dell'Energia Nucleare e delle Energie Alternative (DISP), Italy Bottino, A. Comitato Nazionale per la Ricerca e per lo Sviluppo dell'Energia Nucleare e delle Energie Alternative (DISP), Italy Denham, D.H. Battelle Pacific Northwest Laboratory, United States of America Ehdwall, H. National Institute of Radiation Protection, Sweden Fry, F. National Radiological Protection Board, United Kingdom Fujimoto, K. International Atomic Energy Agency, Austria Gonzalez, A.J. International Atomic Energy Agency, Austria Hamada, T. Japan Radioisotop Association, Japan Hunt, G.J. Ministry of Agriculture, Fisheries and Food MAAF Fisheries Laboratory, United Kingdom Inaba,J. International Atomic Energy Agency, Austria and National Institute of Radiological Sciences, Japan

. Jaworowski, Z. Central Laboratory for Radiological Protection, Poland Kasai, A. Japan Atomic Energy Research Institute, Japan Laylavoix, F. Commissariat a l'energie atomique, Institut de protection et de sarete nucl6 aire, France Madelmont, C. Commissariat a l'energie atomique, Institut de protxtion et de snrete nucidaire, France Measures, M. Atomic Energy Control Board, Canada Mishra, U.C. Bhabha Atomic Research Centre, India s,om m

e Source and Envronmental Montonng for Radiation Protection of the Pubhc 1996-08 29. 4 57pm Consultant Meetings Vienna, Austria: 26 November-14 December 1984,13-17 May,2-6 December 1985, 15-19 September 1986 Advisory Group Meetings Vienna, Austria: 15-19 April 1985,19-23 August 1985,21-25 April 1986, 2-6 December 1996 Consultant Services Vienna, Austria: 21-25 August 1989 Vienna Austria: 30 November - 4 December 1992 Vienna, Austria: 26-30 August 1996 1

SONrth RPT

Figures for a draft of monitoring Guide.

Fig.1. Types of monitoring for radiation protection of the public.  !

l l

Fig.2. Basic Scheme for source and environmental monitoring for radiation protection l of the public.  :

i i

i Fig. 3. Simplified pathways to man of radioactive materials }

released to the atmoshere or water bodies.  !

I t

5 Fig. 4. An example of design of an environmental-monitoring programme ]'

for a major source (from Ref. [2] ).  ;

I i

l i

1 9

i

MONITORING Source Environmental Individual Monitoring Monitoring Monitoring i

Single Multiple Widespread source source source l monitoring monitoring monitoring t

l Fig.1. Types of monitoring for radiation protection of the public k

I

O I w %.l OMb R [

D 2. : . '. ..

i L'u ' t -

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,{ 4 w &m l&

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?"jf Fig. 3. Simplified pathways to man of radioactive materials released to the atmoshere or water bodies.

% -