The Use of Effective Dose as a Radiological Protection Quantity


Draft document: The Use of Effective Dose as a Radiological Protection Quantity
Submitted by Roger Coates, IRPA
Commenting on behalf of the organisation

IRPA Response to the ICRP Consultation on “The Use of Effective Dose as a Radiological Protection Quantity”

1 August 2018

IRPA welcomes the opportunity to provide comments on this draft ICRP report. For this consultation we invited the IRPA Associate Societies around the world to provide comment to IRPA, and we have also reviewed the draft report against IRPA’s current positions which relate to this topic. This response takes the form of a short note identifying the key issues arising from these considerations, together with a list of the full responses of those Associate Societies which responded to our request. The individual Associate Society responses will be forwarded separately to the ICRP consultation.

Headline Issues

Issue 1. We note that the document proposes that Equivalent Dose (H) is not required as a protection quantity, and that it is more appropriate for limits protecting against tissue reactions to be set in terms of Absorbed Dose (Gy) rather than Equivalent Dose (Sv). Whilst the attached annexes contain some detail suggestions for how to move forward in this direction, we did not receive any expressions of concern relating to the overall proposal.

Issue 2. A key proposal of the draft report is that Effective Dose may be considered as an approximate indicator of possible risk, all be it with the need also to give additional consideration of variation in risk with age, sex and populations group. This is described as ‘a pragmatic and unintended application’ of Effective Dose. Whilst in some ways this is perhaps an inevitable and natural step to take, IRPA is concerned that in formalising this approach ICRP is taking a quite major step in the overall context of the system of protection, which must be addressed more explicitly and carefully. The risk assessment method proposed is wholly based on LNT. To date there has been a clear acceptance that LNT is a model (or a hypothesis) purely for the purposes of protection, and it is not a scientific model of risk from radiation. This new formal proposal is therefore a significant step away from this historic approach, towards an inherent acceptance that LNT can be used as the basis for an approximate indicator of risk.

Of course the draft report presents several caveats to this approach – noting that there are many uncertainties associated with risk projection to low doses and low dose rates, and that the associated risks are increasingly uncertain at lower doses. However, in our recent report on IRPA’s consultation on the system of protection (ref below) we noted two very important factors of relevance to this proposal. We were concerned to ensure that as a profession we are always totally honest and accurate in statements concerning radiation risk, and that there is a concern that the system of protection relies too heavily on many detailed caveats, which we termed the ‘fine print’, which are absolutely essential to full understanding but which usually get lost in detailed application and discussions. Our concern is therefore that in practice the new proposals will result in many statements which quite definitively state that the risk (of such and such a procedure, etc) is X, without any visible caveat. Such statements would clearly be inaccurate and give a false impression of what we really know about radiation risk at low dose.

It is therefore essential that ICRP gives further consideration to the introduction of this significant change to the use of LNT, including how this new formal proposal can be framed to help ensure that the limitations of the approach are more clearly delineated and visible, and in particular how to make clearly visible the very significant uncertainty in risk estimates at low doses. It is important to minimise the opportunities for misuse of such risk estimations.

Issue 3. The draft report is a difficult read, with much repetition – both within the document itself and repetition of many prior ICRP statements. There is a need for significant editing which must lead to greater clarity, consistency and improved use of language.

Issue 4. A particular example of repetition is the discussion on collective dose, which is unnecessarily spread across several sections. The text includes several repetitions of previous ICRP statements, without adding any significant new material. This is a missed opportunity, and the report should include a clear ICRP position on use, and particularly the limitations, of collective dose. We draw attention to statements in section 3:

“Collective effective dose is not intended as a tool for epidemiological risk assessment …”: Given that this report is now endorsing the use of effective dose as an ‘approximate indicator of risk’ it would be helpful to make transparently clear the difference between the two types of risk assessments.

“The computation of cancer deaths based on collective effective doses involving trivial doses to large populations is not reasonable and should be avoided”: This gives an opportunity for ICRP to pull together a definitive statement on the reasons for the limitations, which has been lacking to date.

Wider Matters

ICRP’s process of consultation on draft reports is a highly valued contribution to the development of the system of protection. It would be helpful if it is possible to allow somewhat more time for consultees to prepare their responses.

Reference

IRPA Consultation: is the system of protection ‘fit for purpose’ and can it be readily communicated? Views of the radiation protection professionals. R Coates and R Czarwinski. J. Radiol. Prot 38 (2018) 440-455.

Associate Society Responses

Argentinian Radiation Protection Society

Comments to the Draft by the SAR Working Group

 The Working Group welcomes the draft,  a much expected document on the use of effective dose  reflecting an important decision taken by the ICRP to revise and clarify concepts providing further guidance on specific aspects related to conceptual and practical applications in radiological protection following the Recommendations in Publication 103.

The draft remarks the relevance of Effective dose in optimization of protection and to verify compliance, addressing issues focused on the appropriate application in different medical diagnosis and treatment exposures.

A significant change is introduced related to Equivalent dose proposing that it is no longer  required as a protection quantity been replaced by absorbed dose in setting limits for tissue reaction.  It is apparent that a weighting methodology for the absorbed dose should be introduced for tissue reaction  assessment.

The draft reassures Collective Effective Dose as a valuable tool in optimization of occupational protection and remarks the need for careful use discouraging its application as an epidemiological tool or in predicting possible health effect for large population exposed to very low doses over long periods of time avoiding undue expectation on the number of future fatal cases. 

Never the less the WG considers that the use of collective effective dose in screening assessment evaluation and planning  of radiation protection actions are undoubtedly important potential application for which further clarification and guidance is recommended to beg include in the draft.

WG also feels that the writing of the draft should be more adjusted in style and focused as other document releases by ICRP with emphasis to Chap. 5 Medial Exposures.

The table shows comments, most of them of editorial and technical nature proposed by the WG  intended to improve the draft.

 

Line

Text

CommentS

 

ABSTRACT 

 

110, 111, 112, 113

Conclusions are drawn that: a) Equivalent dose (H) is not  required as a protection quantity. It will be more appropriate for limits for the avoidance of tissue reactions for the hands and feet, lens of the eye, and skin, to be set in terms of absorbed dose (Gy) rather than equivalent dose (Sv).

Conclusions are drawn that: a) Equivalent dose (HT) is not  required as a protection quantity. It will be more appropriate for limits for the avoidance of tissue reactions for the hands and feet, lens of the eye, and skin, to be set in terms of mean absorbed dose (DT) rather than equivalent dose (HT).

 

MAIN POINTS

 

185, 186, 187, 188, 189, 190, 191

The dosimetric quantities used in radiological protection are absorbed dose (D), with the special name of gray (Gy), and equivalent dose (H) and effective dose (E), both with the special name of sievert (Sv); the SI unit is J kg-1 in each case. Absorbed dose is calculated for radiological protection purposes as an average over organs and tissues and is the primary scientific quantity from which E is calculated. Absorbed dose is the most appropriate quantity for use in setting limits on organ/tissue doses to prevent tissue reactions (deterministic effects).

The basic physical dose quantity used in radiological protection is the absorbed dose (D). For radiological protection purposes, D is calculated as an average over organs and tissues and is called mean absorbed dose (DT). D and DT SI unit is J kg-1 and their special name is gray (Gy). Additionally, the quantities equivalent dose (HT) and effective dose (E) are used. HT and E SI unit is J kg-1 and their special names is sievert (Sv).Mean absorbed dose (DT) is the most appropriate quantity for use in setting limits on organ/tissue doses to prevent tissue reactions (deterministic effects).

 

INTRODUCTION

 

303

The ICRP protection quantities – equivalent dose (H) and effective dose (E)…

The ICRP protection quantities – equivalent dose (HT) and effective dose (E)…

310

…the calculation of the mean absorbed dose (D) to organs and tissues…

…the calculation of DT to organs and tissues…

312, 313

…the second step is to multiply the calculated values of absorbed dose by radiation weighting factors…

…the second step is to multiply the calculated values of DT by radiation weighting factors…

362

…in Section 3…

…in Section 4

373, 374, 375, 376

Confusion between operational quantities used to measure exposures to external sources and the protection quantities: specifically between dose equivalent (measured quantity for external radiation used as an estimate of effective dose) and equivalent dose (an intermediate quantity in the calculation of effective dose).

Confusion between operational quantities used to measure exposures to external sources and the protection quantities: specifically between dose equivalent (H, measured quantity for external radiation used as an estimate of effective dose) and equivalent dose (HT, an intermediate quantity in the calculation of effective dose).

 

CHAP. 2. HEALTH EFFECTS

 

11

457-461

 The limits for the lens of the eye, skin and hands and feet  are relevant mainly to circumstances of exposure to penetrating low LET radiations.

 However, exposures to neutron and other high LET radiations may require consideration in some situations and it may then be necessary to take account of increased effectiveness per

Gy (ICRP, 1990, 2003b).

 

The limits for the lens of the eye, skin and hands and feet  are relevant mainly to circumstances of exposure to penetrating low LET radiations.

However, in those exceptional radiation protection situations where high-LET effects on the skin or the lens of the eye can occur , the use of an RBE-weighted absorbed dose  will be necessary (ICRP, 1990, 2003b).

 

17 c)

538-542

Transferal of risk estimates across populations: To estimate radiation risk for each  cancer site, a weighting of the ERR and EAR lifetime risk estimates was established that  was considered to provide a reasonable basis for generalizing across populations with  different baseline risks; for example ERR:EAR weights of 0:100% were assigned for breast, 100:0% for thyroid, 30:70% for lung, and 50:50% for others.

Transferal of risk estimates across populations: it is problematic to transfer site-specific estimates of radiation-related risk from one population to the other if the corresponding baseline rates differ.

Therefore, to estimate radiation risk for each  cancer site, a weighting of the ERR and EAR lifetime risk estimates was established with weights based on judgements concerning the relative applicability of the two risk estimates. For example, for breast only an EAR model was used (ERR:EAR weights of 0:100%), for thyroid only an ERR model was assigned (ERR:EAR weights of 100:0%), 30:70% for lung, and 50:50% for others

 

 

 

638

Table 2.2. Detriment-adjusted nominal risk coefficients per effective dose (10-2 Sv-1  )

Table 2.2 . Detriment adjusted nominal risk coefficients per effective dose for cancer and heritable effects (10-2 Sv-1)

 

638

Table 2.2  Third Line: Adults

 It should be  changed : Adult workers aged 18-64

737

Figure 2.1  The ordinate of the graphic: Cancer risk per absorbed doses (% /Gy)

It should be changed by : Cumulative cancer risk per absorbed doses (% /Gy)

 

 

The quantity name or its symbol are  used  indistinctly.  It is recommended to apply through the text the same criteria in the way to designate quantities.

 

 

CHAP. 3. DOSIMETRY

 

874, 875

The values of wR were selected largely on the basis of measurements of relative biological effectiveness (RBE) of the different radiations.

The values of wR were selected largely on the basis of measurements of relative biological effectiveness (RBE) of the different radiations which are relevant to stochastic effects.

 

CHAP. 4. OCCUPATIONAL AND PUBLIC EXPOSURES

 

 

 

 

1359

 

Add at the end of para.: and if the case provide precise dose information to the intervening medical staff in order to help in establishing the prognoses for possible tissue reactions

1396

 

Should read: Exposure to external and internal sources in planned exposure situations  occur in a range of situation

1422

the hypothetical person

Change to: the Reference Person  and in capital letters throughout the draft.

1510

many situations

Change to: most situations

1528

Prospective assessment of pre-operational facilities and for emergencies.

Change text to: prospective assessment of facilities at pre-operational stage and for emergencies

1536

Heading 4.3 Collective dose assessment

should  read: Collective effective dose assessment

 

CHAP. 5. MEDICAL EXPOSURES

 

 

 

 

1753

Heading,  Reporting of unintended exposures

Should read:  Reporting of unintended and accidental  medical exposures

1754

Unintended  exposures and overexposures of patients  in diagnostic procedures

Should read:  Unintended  exposures and overexposures of patients  in diagnostic and treatment procedures

1686

Values of effective dose for a reference person are included in many guidelines for referral and justification

 

Include reference to existing guidelines

1719/ 1720/ 1721

 

The basic aim of  optimisation of protection is to adjust the protective measures in a way that adequately  addresses the clinical question while keeping the radiation dose to a minimum or to as low as  reasonably achievable (the ‘ALARA’ principle) (ICRP, 2007a).

The basic aim of optimization of protection is to adjust the protective measures in a way that adequately addresses the clinical question while keeping the radiation to as low as reasonably achievable (the ‘ALARA’ principle) (ICRP, 2007a).

1754

Unintended exposures and overexposures of patients in diagnostic procedures

Unintended exposures of patients in diagnostic procedures.

 

(overexposure is an unintended exposure; and the title is “Reporting of unintended exposures”)

 

1759/1760/1761

An overexposure might occur when there has been a mistake in the procedure technique, or where an equipment fault has occurred (Martin, 2005; Martin et al. 2017).

 

Example,

An unintended exposure could occur in various situations, such as when there has been an error in the referral process or the wrong patient or body part was examined or when overexposure occur because of a failure or wrong operation of the medical equipment

1795 to 1798

 

Clinicians who refer and other medical professionals who perform medical procedures involving radiation may have little understanding of the potential health detriment from radiation exposure, because it is so small compared to the benefits of medical exposures  (ICRP, 2009b; Loose et al., 2010; Zanzonica and Stabin, 2014).

 

This paragraph should be rewritten addressing the need for an adequate training in radiation protection  of clinicians in order to recognize the risk at low doses

 

1798 to 1804

 

Consequently, it is difficult for them to take these potential risks into account when requesting or justifying patient diagnostic or interventional exposures, or when explaining possible risks to their patients.

 

 

Idem, need for training and refreshing

 

 

1805/1806/1807

Medical practitioners are also one of the first groups approached by members of the  public for advice and reassurance in the event of a radiation exposure or an accident involving potential radiation exposure of the public

 

This paragraph doesn’t seem to fit in this chapter.

 

(114)

 

Table 5.2 gives a scale linked to effective dose, with general terms to describe the dose linked to possible levels of risk and examples of procedures within different dose ranges. The terms used for effective doses of 1 mSv and greater are the same as applied by UNSCEAR (2012a) to whole-body absorbed doses (mGy) in the same ranges.

 

The text should be improved to better reflect the content of the referred paragraph, using preferentially “bands of exposure” to describe ranges of dose.

 

 

Table 5.2

“Effective doses (mSv)

Change to

 “range of effective dose (mSv)”

 

 

Table 5.2

Proposed term for dose level

 Change to:

“terminology of dose bands”.

 

Table 5.2

Examples of medical radiation procedures within different dose categories

 

 

Change to

Examples of medical radiation procedures within different range of effective dose

 

 

Table 5. 2 Proposed term for dose level

Negligible/ minimal/ very low/ low/ moderated

The term   “minimal” does not correspond with the other dose level terms

1842

Table 5.2

In last line, “100s”

Greater then 100 mSv

 

1842 / 1843 / 1844

Table 5.2. Dose ranges and terminology for describing risks from different medical procedures for adult patients of average age (30-39 years) based on UK data (Martin, 2007a; Wall et al., 2011; Martin and Sutton, 2014).

Included the ICRP reference as in Line  1847:

Effective doses based on UK for diagnostic procedures and ICRP (2010b) for interventional  radiology

1825

(115) Clinicians and patients will sometimes need more information in order to put radiation exposures and possible risks into context. …

 

For this role clinicians shall be trained in radiation protection

 

1863

(117) Based on the methodology described in section 2.6 to calculate lifetime risk of cancer incidence per unit organ/tissue absorbed dose, and using UK estimates of organ/tissue doses  from a range of medical procedures, Wall et al. (2011) derived age- and sex-specific risks per  unit effective dose for such procedures.

 

Include reference to  “UK estimates”

 

Fig 5. 1  (Asian population)

Add a figure for Euro-American population  following  Table 5.3

 

German-Swiss Society of Radiation Protection

It seems to be that the only thing that''s new here is the new treatment of the organ equivalent dose? Scientifically, it may be partly right, but the implementation is exaggerated, just because one could confuse the mSv of E with the mSv of HT. For the user and especially for the layman, it is difficult to understand that we should now use two units, which are (except if wR¹1) of the numerical value in about the same size. Why the whole thing? Indeed, a difference in numerical value is only where the wR factor is different from 1, so it can only affect radiological events, e.g. thyroid doses or organ doses after incorporation after an incident. Normally, we are doing well with E, and we need neither the organ equivalent dose nor the absorbed energy. In addition, HT seems problematic for the lungs unless we have a working dosimetric model.

Summing up, the whole thing is of a very sophisticated scientific level and it is not needed in practice. The definition of the dose quantities have ever been a work of scientists which have never been understood to the full by the practitioners. But this was never a problem for doing radiation protection. The level of occupational doses have reached a very low state. And we do not need to make the system more complicate or change the way it works due to scientific reasons.


Italian Association for Radiation Protection

The draft report appears to be a comprehensive review of the basis for the correct application of the concept effective dose. The report confirms that the system of radiological protection recommended by ICRP is basically sound and possible adjustments suggested by the report are of a rather theoretical nature and do not require an immediate impact on existing legislation and current procedures.

Specific points:

· Paragraph 75. In the formulation of the text, exposures due to naturally occurring radioactive materials in industry seem to be considered existing exposure situations, apart from single decisions to put under control the concerned activities. Actually, the international radiological protection frame regarding NORM activities has been reversed in the last years (IAEA BSS). NORM activities are generally managed as planned exposure situations, taking into account, nevertheless, the occurrence of possible exemption conditions. This perspective has already been adopted in International contexts, including EU BSS (Euratom Directive 2013/59).

· Table 2.5 caption: ‘…cases power per 100 per Gray…’

· Table 2.5 note: ‘…ERR/EAR of 100/0 for thyroid, 30/70 for lung, 0/100 for breast, 50:50 for all others)…’ Notation has to be standardised (in the text – lines 541 and 542 – the colon is used).

· Lines 645-647: Effective dose is a weighted average of equivalent doses to organs and tissues, used as a measure of whole-body dose (see also line 954). This is at variance with ICRP 103, whose definition of effective dose is: The tissue-weighted sum of the equivalent doses…

· In the paragraph 4.1 there are at least two apparent out of topic related to the measurements methods (1301-1306) and to the exposure protection (1372-1373). These aspects are very interesting but should require specific reports or recommendations, here they appear to be improperly placed.

Prepared by AIRP-International Committee

 

Japan Health Physics Society

GENERAL COMMEMTS

  We can understand the concept of changing the settings of dose limit from equivalent doses to absorbed doses to prevent tissue reaction. However, practical guidance on how to actually use absorbed dose limit to avoid non-cancer effects should be prepared until new main recommendations are issued. It has not been clarified yet how we should use the absorbed dose including RBE, particularly for high-LET radiation. Pub. 118 did not provided updated knowledge on high-LET radiation. For skin and extremities, wR can be used for absorbed dose limits for skin and extremities, because RBEM and RBEm have been compared. However, for the lens of the eye, such comparison has not been made, and RBE will thus be more appropriate.

  The summary of the October 2012 Main Commission meeting states “the use of the special name sievert without proper context can cause confusion, and therefore recommends that the quantity (effective dose or equivalent dose) always be specified. Furthermore, when used for equivalent dose the relevant organ must also be specified”. This statement may be explicitly described in this report, i.e., noting that “when used for absorbed dose the relevant organ must also be specified”.

  This document is a supplementary guideline for the use of effective dose described in Publ.103. So, ICRP should give us a possible scientific evidence for the items mentioned in this document as a reference. For example, in this draft document para. (46), it is mentioned that “for doses in excess of 100mSv delivered at high dose rate, a DDREF of two applied in determining solid cancer risk at low dose /dose rates will not apply”. ICRP should identify the value of high dose rate above which a DDREF of two is not applicable to evaluate radiation risk at an actual field while showing the scientific evidence.

  According to the report of TG84 they mentioned that the lack of a formal quantity for a radiation-weighted dose for high doses was an issue in the current radiological protection system. We think that ICRP should add the comment to this issue in this draft document.

SPECIFIC COMMENTS

Main Points lines 241-242 Section 3.7 (63)

  As described in this draft document (63) the use of committed doses introduces conservatism into calculation of doses from annual intakes for the radionuclide with long half-lives and long retention time, which should be reconsidered to avoid irrational anxiety or excess concern about internal exposure among the public and workers.

Main Points lines 221-223 Section 6 (126) line 2020-2022

  “its use exceptionally in emergency exposure situations at acute doses in the range up to around 1 Sv (or the order of several 100 mSv) is reasonable” ß For managing short term exposure of the Fukushima emergency workers (age >40 with low risk for radiogenic thyroid cancer), the equivalent dose to the thyroid was added to effective dose (in the same way as for the planned exposure situation). There is the possibility that this impeded emergency responses or led emergency workers to increase their anxiety. As such, for management of dose to emergency workers, other index may be considered, taking into account mortality, lethality or severity of health effects.

Section 6 (122) lines 1963-1973

  ICRP is required to clarify the following points in advance. In updating the dose limit associated with non-cancer effects, ICRP should consider the establishment of a factor substituting the radiation weighting factor so that radiation risks can be easily evaluated even in a mixed radiation field.

・Concept of setting the dose limit (how are the effects of high LET radiation and the distribution of tissue doses incorporated in setting the dose limit)

・Evaluation of doses associated with non-cancer effects (a specific way of evaluating doses in the work place exposed to mixed low and high LET radiation)

Section 6 (126) lines 2025-2028

  The paragraph(126) describes the thyroid tissue reaction; if there was a significant contribution to the effective dose from radionuclides concentrated in particular organs (e.g., iodine-131 in the thyroid, inhaled insoluble radionuclides in the lung),tissue damage could occur. Notable for 131I, for example, an effective dose of 250 mSv could correspond to a thyroid dose of >6 Gy. On the other hand, ICRP Publ. 41 notes that if the whole thyroid is exposed to approximately 25~30 Gy x-ray doses in fractions for 30 days, it could result in serious functional damage. It is necessary to clearly describe the effects that may be caused by the difference in the thyroid tissue reaction from Publ. 41 description.

Section 3.7 (64) lines 1209-1213

  Dose coefficient for internal exposure due to radiopharmaceuticals has been provided for age groups, but the control of public or occupational exposures does not include medical exposure. This statement may need to be added.

Section 4.2 (88) lines 1522-1524

  “It is important to balance the reduction in doses with any deleterious effects of the action and a cautious assessment of doses could lead to unnecessary actions with adverse consequences for the affected population.” ß For optimization purposes, a balance between the degree of caution and efforts for dose reduction is important in any exposure situations. To clarify this, the following revision of the sentences is proposed. ”It is important to balance the reduction in doses with any effort or resource to reduce dose in any exposure situation. Particularly in an emergency exposure situation, a too cautious assessment of doses could lead to unnecessary actions with adverse consequences for the affected population.”

Section 5.4 Table 5.2

  It needs to be explicitly stated that this table is only dedicated to risk communications for medical exposures of adults. From the viewpoint of risk communications, it is important to touch on epidemiological observability as was done in Table 1 of Publication 96. In the second column from the left, it needs to be stated that risk at <0.1, 0.1-1, 1-10 mSv is also based on LNT in addition to that at 10-100 mSv. The label for the second column from the right may be changed from “Proposed term for dose level” to “Proposed term for dose level in medical exposure of adults”

Section 1 (3) lines 327-328

  The need to define the concrete level of low dose rate is unclear, and it may be better if only the order of magnitude is described while describing the relevant numbers: e.g.,

Section 1 (6) lines 368-370

  “The use of equivalent dose in setting limits for the avoidance of tissue reactions in the cases of irradiation of the hands and feet, lens of the eye, and skin; that is, limits set below thresholds for the occurrence of acute damage to organs and tissues.” ß “acute” needs to be deleted. Take cataracts and circulatory effects for instance: these thresholds are set for effects occurring at >20 years and >10 years after exposure, respectively.

Section 1 (6) lines 370-372

  “In general, smaller differences in effects per Gy are observed between radiation types in relation to tissue reactions than stochastic effects (ICRP, 2003b).” ß This does not apply to the lens because the lens does not develop tumors.

Section 2.2 (10) lines 440-443

  “However, the available data indicate that differences between radiation types (e.g. alpha particles and neutrons relative to gamma rays) in their effectiveness per Gy in causing tissue reactions are smaller than differences in their effectiveness in relation to cancer induction (ICRP, 1990, 2003b).” ß This does not apply to the lens of the eye, because the lens does not develop tumors.

Section 5.1 (97)

  Dose conversion coefficient for effective dose due to external exposure and dose coefficient for committed effective dose due to internal exposure should distinctively be described.

Section 5.4 (116) lines 1853-1854

  “Depending on the risk projection models used, there are also differences between populations.” ß Risk can differ among populations, but population transfer is used for simplification.

Section 6 (122) lines 1970-1973

  “This change to the use of absorbed dose rather than equivalent dose would not require changes to the numerical values of dose limits for tissue reactions and will be considered by the Commission when new general recommendations are formulated.” ß It is unclear what the Commission will consider upon formulation of the new general recommendations.

Section 6 (125) lines 1997-2000

  “It has been argued that this approach does not adequately protect women and younger children and that differences between males and females and greater risks at younger ages should be reflected more explicitly in the ICRP system, including the use of different detriment values and wT values.” ß Detriment is used only for deriving wT. As such, age-, sex-dependent detriments have no specific functions in the system of radiological protection as indicated in Table A.4.18 of Publication 103.

Section 6 (126) lines 2028-2033

  “A secondary consideration is that for doses in excess of 100 mSv (or more precisely, absorbed doses to organs and tissues > 100 mGy) delivered at high dose rate, the DDREF of 2 applied in determining solid cancer risk at low doses will not apply, so that risks may be somewhat greater than might be assumed on the basis of Publication 103 (ICRP, 2007a) nominal risk coefficients.” ßThe risk posed by acute exposure to >100 mSv can directly be estimated based on epidemiological evidence, rather than with the nominal risk coefficients.

EDITORIAL COMMENTS

Section 2.6 (21) lines 687-688

  “Risk of Exposure-Induced InCidence (REIC)” may be changed to “Risk of Exposure-Induced Cancer”

Section 3.2 (34) line 841

  "clinical radiology” may be changed to “radiology, radiation oncology”.

Section 3.5 Fig 3.2

  "reference phantoms” in the title may be changed to “adult reference phantoms”.

Section 3.6 (54) lines 1085-1087

  “The standard approach to the calculation of skin doses is to determine the average dose to the most exposed 1 cm2 at a depth of 70 μm (ICRP, 1991a, 2007a)” ß The local skin dose is defined by the mean equivalent dose in 0.07 mm depth averaged over any 1 cm2 of the skin, regardless of the area exposed.

Section 3.7 (58) lines 1143-1147

  “the increased importance of the lens of the eye with the reduction in the dose limit to 20 mSv per year (ICRP, 2012a) has led to a re-evaluation of its application (ICRP, 2010a; Bolch et al., 2015).” ß “20 mSv per year” may be changed to “20 mSv/year year, averaged over defined periods of 5 years, with no single year exceeding 50 mSv”.

 

Korean Association for Radiation Protection

Hak Jae Kim, Professor, Seoul National University Hospital, Korea

The values in Table 5.3 and 5.4 should be re-checked. In Table 5.3, which shows the total lifetime risks for the ICRP Euro-American composite population, there is no significant difference in risk between males and females for the examination of Head (AP+PA+Lat), while the risk is quite predominant in males for the examination of CT Head.

On the other hand, in Table 5.4, which shows the total lifetime risks for the ICRP Asian population, the relationship of risks is reversed; that is, in Table 5.4, the risk is predominant in females with the examination of Head (AP+PA+Lat), while there is no significant difference in risk between males and females for the examination of CT Head.

It should be noted that in Wall et al. (2011, Radiation Risks from Medical X-ray Examinations as a Function of Age and Sex of the Patient. HPA Report HPA-CRCE-028. Chilton), the risk of cancer incidence is predominant in both males and females.

 Jeong In Kim, Researcher, KHNP Radiation Health Institute, Korea

The collective dose should be eliminated or should be recommended with a specific lower bound for dose integration. In the latter case, ICRP should provide the value of the lower bound for integration, preferentially in this report, to address the problem that the collective dose is misused to predict effects on health in large populations, large areas, and over extended time periods.

Please note that paragraph (69) concludes that the estimates of the individual effective dose and collective effective dose can be used to optimize the protection. However, the necessity of collective effective dose is not clearly demonstrated in the report. It is believed that the distribution of individual effective dose values provides enough information to optimize protection.

Paragraph (92) argues the usefulness of collective effective dose in situations of severe nuclear accidents. In this case, the collective effective dose could be used with a lower bound for integration. However, again, the value of the lower bound should be provided by ICRP.

 

Romanian Society for Radiological Protection

1.- We have nothing against to the idea that effective dose can be used as a rough indicator of risk in some circumstances. Many reasons for estimation of the effective dose as a "rough indicator" are included in this draft report itself.

2.- Regarding the proposal to stop the use of equivalent dose as an important radiological protection quantity we have some doubts. All we know that any organ/tissues radiation effect is strongly determined by the local absorbed dose and on the LET of the radiation involved. Particularly, in the very frequent medical situation of  non-uniform spatial distribution of a mixed radiation field , the use of dose limits expressed in equivalent dose may be more appropriate to be "continued", than to be "discontinued". We may agree only on that the use as a distinct protection quantity is not required, but its use still is essential in individual monitoring, external dosimetry of lens of eye, skin and extremities and in internal dosimetry.

3.- In chapter 5 regarding MEDICAL EXPOSURE, the given examples for supporting effective dose as an important protection quantity are valid only in diagnostic radiology practice. Particularly, in nuclear medicine and in radiotherapy the equivalent dose in specific organ/tissue may be more significant than the effective dose. Even in diagnostic radiology, for optimisation of radiation protection of an individual patient, the use of DRLs in terms of measurable quantities is  more effective than the proposed effective dose.

3.- We fully agree that:

- Several confusions between the equivalent dose and efective dose arised from the use of a same name for the unit  (Sievert).  This may be simply solved by given (by ICRU/ICRP) of a separate name to one of them. Additionally, we may add confusions between the equivalent dose and the operational quantity dose equivalent, and that between "reference" person and "representative" person.

- There is a real need to develop in the future appropriate tissue weighting factors depending on age, sex and cancer type.

- The prudent approach in the draft report for some declared assumptions in the context of practical implementation of the radiological protection system, particularly regarding the use of collective dose in the context of risk projection should be appreciated, but we consider that no important changes are presented here, in comparison with the recommendations already available in ICRP the 103. Also, the same  known  statements from ICRP 103 are unuseful repeated in  several chapters of the  draft report and this should be avoided in the final version.

Constantin MILU, Ph.D.

RSRP President

Bucharest, 13 July 2018


Spanish Radiation Protection Association

196-197

444

454

 

Main Points

(10) – (11)

(44)

 

The statement “the use of equivalent dose to set limits on organ/tissue doses to prevent tissue reactions should be discontinued” should be cautiously introduced in the radiological protection system. Although the reasons for this change are well justified in several parts of the report, it is a main change and we consider that its implications are not discussed in the current draft with the necessary detail. For instance, it would require a rather complex definition of organ dose limits. Since limits on organ doses are intended to prevent tissue reactions, using absorbed dose given the variable RBE of particles like neutrons, depending on their energy would force to set variable absorbed dose limits for an organ depending on the energy and type of the radiation particles, and this cannot be easy to manage. As it is recognized in the text (11): “However, exposures to neutron and other high LET radiations may require consideration in some situations and it may then be necessary to take account of increased effectiveness per Gy”. How to introduce a practical approach to organ limits under these conditions?

The report should give some advice on the way in which new organ/tissue dose limits to prevent tissue reactions could be developed, with particular attention to complex situations involving mixed fields (low and high LET), mixed exposure internal-external, neutrons, etc.

221-227

 

Main Points

 

The definition and application of E would be clearer if the paragraph “Although E will generally be used at doses below 100 mSv, its use exceptionally in emergency exposure situations at acute doses in the range up to around 1 Sv is reasonable, noting that the possibility of occurrence of tissue reactions should also be considered at such doses if a significant contribution is made by non-uniform distribution of external dose or radionuclides concentrated in specific tissues/organs” would be moved up in the text, to line 206.

Move this paragraph to line 206

246-248

 

Main Points

 

The sentence “Effective dose coefficients for the fetus following intakes of radionuclides are provided for comparison with dose for other age groups, showing that it is only in the case of a few radionuclides that fetal doses may need to be considered” may be completed with the radionuclides of interest for foetal doses

“Effective dose coefficients for the fetus following intakes of radionuclides are provided for comparison with dose for other age groups, showing that it is only in the case of a few radionuclides that fetal doses may need to be considered (e.g. internal exposures to ------)”

254

 

Main Points

 

It is said that “In medical applications, estimates of E to Reference Persons are used for comparing doses from different diagnostic and interventional imaging modalities”. It’s necessary to emphasize that “the potential risk from medical exposures is generally lower than for a reference population due to the higher average age of patients and competing disease related risks with reduced life expectancy, although paediatric populations serve as an exception”, as mentioned in lines 1835-1838 of paragraph 115.

Include the sentence “The potential risk from medical exposures is generally lower than for a reference population due to the higher average age of patients and competing disease related risks with reduced life expectancy, although paediatric populations serve as an exception”, as part of this main point

318

 

1 Introduction / (2)

 

“effective dose is a weighted average of organ/tissue doses”

“effective dose is a weighted average of organ/tissue equivalent doses”

620

 

2.4 Nominal risks coefficients and detriment / (18)

Table 2.1

This table reproduces the values of Table A.4.1 of Publication 103 where the Nominal Risk Coefficients are expressed in cases per 10.000 persons per Sv (equivalent dose). However, Table 2.1 expresses the same coefficients but per Gy (absorbed dose). If the values of Publication 103 were calculated per unit of equivalent dose (radiation weighting factors considered), it is not clear that the values per Gy remain the same, even when the table caption indicates that values are for uniform whole body exposure to gamma rays, which apparently was not specified in Table A.4.1.of Pub. 103.

Clarify this aspect

830

 

3.1 Dose quantities / (33)

 

Typing mistake: “fndamental”

“fundamental”

933

 

3.7 Operational quantities and dose assessment / (57), (58), (59)

 

As regards the definition of the operational quantities, on the one hand the definitions of Hp(d) and H*(10) as defined in ICRU 47 and 51 and ICRP 103 are given (paragraphs 57, 58), while on the other hand paragraph 59 refers to the new operational quantities now under revision.

This paragraph (59) in its present form is confusing.

 

It would be better to have a more agreed version of the ICRU new operational quantities before finalizing paragraph 59

1004

 

3.5 Dose coefficients / (49)

 

Recalculation of dose coefficients of internal exposures: A lot of information and references here are missed. New OIR (Occupational Intakes of Radionuclides) Reports should be mentioned because OIR Parts I (methodology), II and III are already published as ICRP 130, 134 and 137 Reports, respectively (and they are already included in the list of references of this document and mentioned in paragraph (53)-line 1077).

Dose coefficients calculated according to ICRP 107 recommendations and using ICRP 110 Reference phantoms are available yet for several radionuclides, for occupational exposures (see OIR Publications II and III). ICRP C2 made available a Dataviewer for a rapid download from ICRP web site of bioassay data and dose coefficients per unit intake, as well as the new coefficients of Dose per Content, as an annex of OIR Reports already published. OIR Part IV will be published soon. OIR Part V later on.

Complete this paragraph with updated information

Introduce the concept of Dose per Content about the use of Effective Dose when addressing internal exposures

1197

3.7 Operational quantities and dose assessment / (64)

 

It is said that effective doses for medical exposures are calculated using dose coefficients that relate measurable quantities to the protection quantities, although note that ICRP has not published reference values. We feel that this document should include a summary table with the suggested “best current coefficient values” to estimate effective doses from the measurable quantities (ESAK, KAP, DLP, radiopharmaceutical activity, etc.) including paediatrics for the different age bands. This should be the best approach to estimate effective doses in Medicine for comparative purposes and to harmonise the estimation of collective doses published by UNSCEAR.

Consider to include a summary table with the suggested “best current coefficient values” to estimate effective doses from the measurable quantities (ESAK, KAP, DLP, radiopharmaceutical activity, etc.).

1281-1309

4.1 Occupational Exposures / (71)

 

This paragraph is too long.

Suggestion to break it at line (1296) when new situations are discussed

1377

4.1 Occupational Exposures / (77)

 

“… and internal exposures from radionuclides that concentrate in particular organs.”

 

Add iodine in the thyroid as the most relevant organ :

“… and internal exposures from radionuclides that concentrate in particular organs, like iodine in the thyroid.”

1408-1410

4.2. Public Exposures / (80)

 

It is written: “Ideally such assessments would be based on monitoring of people and the environment but this is not always possible as the levels are too small to be detected.”

In these cases, effective dose to people is also assessed by using models.

Suggest to complete the sentence:

“Ideally such assessments would be based on monitoring of people and the environment but this is not always possible as the levels are too small to be detected and thus effective dose to people is also assessed by using adequate modelling.”

1428-1451

4.2. Public Exposures / (83)

 

This paragraph is too long and addresses different topics.

Suggestion to break it at line (1441) when retrospective assessments are discussed

1532-1534

4.2. Public Exposures / (89)

 

“When no monitoring data are available, the cautious approach for dose assessment is the selection of those radionuclide characteristics and dose coefficients that result in higher dose estimations.”

Indeed, while this conservative approach is useful in prospective assessments for planned situations, it may be not adequate for managing post-accident existing situations, while realistic models and parameters should be selected to avoid overly conservative assessment of doses that may result in far-from-optimal countermeasures implemented. 

Rewrite the sentence to take into account the comment.

Suggestion: “When no monitoring data are available, the cautious approach for dose assessment is the selection of those radionuclide characteristics and dose coefficients that result in higher dose estimations. However, this conservative approach may be not adequate for managing post-accident existing situations, while realistic models and parameters should be selected to avoid overly conservative assessment of doses that may result in far-from-optimal countermeasures implemented.”

1551-1555

 

 

 

4.3 Collective doe assessments / (92)

 

On collective effective dose, it is written (1228-1232):

“Collective effective dose is not intended as a tool for epidemiological risk assessment and it is inappropriate to use it in formal risk projections for such studies. In particular, the computation of cancer deaths, based on collective effective doses involving trivial exposures to large populations, is not reasonable and should be avoided (ICRP, 2007a).”

But in lines 1551-1555 it seems that suggests estimating health effects from collective dose:  “However, there can be situations where the estimation of health effects from collective effective doses can be useful for planning of radiation protection actions if treated with appropriate caution. For example, following a severe nuclear accident or in advance planning for such events, an assessment of collective effective dose could be used to give an indication of possible health impact to help with planning and selecting from various protection options. “

 

Suggestion to modify this sentence in paragraph (92), deleting mention to estimation of health effects:

“However, there can be situations where the estimation of collective effective doses can be useful for planning of radiation protection actions if treated with appropriate caution. For example, following a severe nuclear accident or in advance planning for such events, an assessment of collective effective dose could be used to give an indication of the overall radiological impact to help with planning and selecting from various protection options.“

 

1593

 

5. Medical Exposures

 

Doses to foetus in medical examinations of pregnant patients should be considered

Include information about doses to foetus in medical examinations of pregnant patients

1899-1911

 

5.4 Effective dose and risk communication

Tables 5.3 and 5.4

Tables 5.3 and 5.4 should be presented for anatomical regions and per mSv instead of for specific x-ray examinations as many other factors should be considered when referring to specific medical examinations. For example, CT examinations can be very complex, include one or more series, and with or without contrast injection. These factors should be also considered.

These tables do not facilitate the risk communication to patients.

Present values per mSv and per anatomical regions

2310

 

References

 

ICRU, in preparation. Operational Quantities for External Radiation Exposure. International Commission on Radiation Units and Measurements.

ICRU, in preparation. Operational Quantities for External Radiation Exposure. International Commission on Radiation Units and Measurements

General

 

 

A glossary of terms would be appreciated, mainly to clarify definitions as Reference Person, Representative Person, Reference population, Paediatric population, etc.

Include a Glossary of Terms section

 

UK Society for Radiological Protection

SRP believes that the proposed changes in the ICRP document are reasonable and pragmatic from an occupational dosimetry perspective.

One issue that has not been addressed is the retrospective calculation of organ/tissue ‘doses’ for compensation scheme / litigation purposes (and possibly also relevant for epidemiology studies).  In such cases the end point is often to derive a dose relationship to a diagnosed cancer in a specific organ/tissue; in such cases the use of Absorbed Dose would not be appropriate, and Equivalent Dose (or some similar quantity which retains a radiation-weighting factor) would still be more appropriate (ie the incidence of biological/clinical effect is of a stochastic from rather than deterministic).

SRP note that some believe that over the years ICRP has sometimes been guilty of change for change sake.  With average annual occupational doses being steadily reduced (typically less than 2 mSv) is a change to Gray really necessary and might it undermine public confidence in the system of radiological protection?

The main advantages of the use of effective dose and Sieverts were that it allowed the addition of assessed doses from various sources eg internal, external and individual organ doses in some sort of logical fashion, and that it allowed some account to be taken of risk and lifetime risk.  The main disadvantage being that you can''t measure Sieverts directly in metrology terms.

 There is of course always the option for regulatory authorities to continue to set dose limits in Sieverts if ICRP choose to recommend constraints or similar in Gray?

With regard to eye lens SRP notes that the cause and effect to the eye lens has to be primarily a Deterministic effect. Although arguments are made to apply dose as Stochastic for the eye lens this is primarily based on use or application to Occupational Exposure. ICRP should make this argument transparent. This would help with control for occupational dose limits as now applied in Legislation for Work with Ionising Radiation. Noting there is no weighting factor for the eye lens.  ICRP then need to comment on a difference between occupational exposure and emergency exposures in relation to setting dose limits and the appropriate quantity to use in both situations. Clearly should there be an emergency exposure (to an operator, responder or member of the public) this is most likely a one off lifetime occurrence (unlike that for occupational exposure).  ICRP would help to comment on appropriate dose quantity and limits to use for the eye lens in an emergency to differentiate between what are two different types of situations and consequences to those exposed to ionising radiations where the dose to the eye lens could be used for both Deterministic and Stochastic parameters.

We note the detailed additional comments from Sellafied Limited and our member Graham Smith.

Additionally we endorse the comments of the IRPA.


Back