NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 1 
SUBSIDIARY LEGISLATION 365.15 
NUCLEAR SAFETY AND RADIATION PROTECTION 
REGULATIONS 
19th May, 2003 
LEGAL NOTICE 44 of 2003. 
ARRANGEMENT OF REGULATIONS 
Regulations 
Part I General Provisions 1 - 4 
Part II Physical Protection of Nuclear Material 5 - 8 
Part III Radiation Protection Board 9 - 16 
Part IV Notification and Authorisation 17 - 19 
Part V Justification, Optimization and Dose Limitation for Practices 
or Work Activities 20 - 24 
Part VI Estimation of Effective Dose and Principles of Operational 
Radiation Protection 25 - 27 
Part VII Classification of Exposed Workers, Apprentices and 
Students 28 - 30 
Part VIII Measures for Restriction of Exposure 31 - 36 
Part IX Workplace Monitoring 37 - 41 
Part X Duties of Persons in relation to Practices, Work Activities 
and Sources 42 
Part XI Medical Surveillance of Exposed Workers 43 - 46 
Part XII Significant Increase in Exposure due to Natural Radiation 
Sources 47 - 48 
Part XIII Implementation of Radiation Protection for the Population in 
Normal Circumstances 49 - 52 
Part XIV Intervention 53 - 59 
Part XV Arrangements for the Control of Radioactive Substances, 
Articles and Equipment 60 - 66 
Part XVI Enforcement 67 
SCHEDULES 
First Schedule Particulars to be provided in a Notification under regulation 17 
Second Schedule Quantities and Concentrations of Radionuclides 
Third Schedule Dose Limits for Different Classes of Persons 
Part 1 - Dose Limits for Apprentices and Students 
Part 2 - Dose Limits for Exposed Workers 
Part 3 - Women of Reproductive Capacity 
Part 4 - Other Persons 
Fourth Schedule Particulars to be entered in the Radiation Passbook 
Fifth Schedule Particulars to be contained in a Health Record 
Sixth Schedule Convention on Physical Protection of Nuclear Material

2 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Annex I - Levels of Physical Protection to be applied in International 
Transport of Nuclear Materials as categorized in Annex II 
Annex II - Categorization of Nuclear Material 
Seventh Schedule Protection of Workers Undertaking Intervention

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 3 
PART I 
GENERAL PROVISIONS 
Citation. 1. The title of these regulations is the Nuclear Safety and 
Radiation Protection Regulations. 
Scope. 2. (1) The scope of these regulations is to: 
(i) allow beneficial and justified uses of ionizing 
radiation; 
(ii) provide for adequate protection of people in 
current and future generations against the 
harmful effects of ionizing radiation and for the 
safety of radiation sources; 
(iii) provide for the physical protection of nuclear 
material; 
(iv) provide a mechanism whereby these objectives 
are achieved through the establishment of a 
Radiation Protection Board to act as the 
competent national authority, by co-ordinating 
the activities of the regulatory authorities in the 
field of nuclear safety and radiation protection. 
Interpretation. 3. (1) In these regulations, unless the content otherwise 
requires: 
"absorbed dose" (D) means the energy absorbed per unit mass 
D = de/dm 
where de is the mean energy imparted by ionizing radiation to the 
matter in a volume element, dm is the mass of the matter in this 
volume element. 
In these regulations, absorbed dose denotes the dose averaged 
over a tissue or an organ. The unit for absorbed dose is the gray; 
"accelerator" means an apparatus or installation, in which 
particles are accelerated, emitting ionizing radiation with an energy 
higher than 1 mega-electron volt (MeV); 
"accident'' means any unintended event, including operating 
errors, equipment failures or other mishaps, the consequences or 
potential consequences of which are not negligible from the point 
of view of protection or safety; 
"accidental exposure" means an exposure of individuals as a 
result of an accident. It does not include emergency exposure; 
Cap. 365. "Act" means the National Interest (Enabling Powers) Act; 
"activation" means the process through which a stable nuclide is 
transformed into a radionuclide by irradiating with particles or 
high-energy gamma rays the material in which it is contained; 
"activity" (A) means the activity, A, of an amount of a 
radionuclide in a particular energy state at a given time and is the 
quotient of dN by dt, where dN is the expectation value of the 
number of spontaneous nuclear transitions from that energy state in 
the time interval dt: 
A = dN/dt

4 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
The unit of activity is the becquerel; 
"ambient dose equivalent" means the quantity H*(d) at a point in 
a radiation field, defined as the dose equivalent that would be 
produced by the corresponding aligned and expanded field in the 
ICRU sphere at a depth d on the radius opposing the direction of 
the aligned field. A depth d = 10 mm is recommended for strongly 
penetrating radiation; 
Cap. 424. 
"Appeals Board" shall have the same meaning as is assigned to it 
by article 2 of the Occupational Health and Safety Authority Act: 
"apprentice" means a person receiving training or instruction 
within an undertaking with a view to exercising a specific skill; 
"approved" means approved for the time being in writing for the 
purposes of these regulations by the Board, and published in such 
form as the Board or the considers appropriate; 
"approved dosimetric service" means a body responsible for the 
calibration, reading or interpretation of individual monitoring 
devices, or for the measurement of radioactivity in the human body 
or in biological samples, or for assessment of doses, whose 
capacity to act in this respect is recognized by the Board; 
"approved medical practitioner" means a medical practitioner 
responsible for the medical surveillance of category A workers, as 
defined in regulation 43(1), whose capacity to act in that respect is 
recognized by the Board; 
"approved occupational health service" means a body or bodies 
to which may be assigned responsibility for the radiation protection 
of exposed workers and/or medical surveillance of category A 
workers and whose capacity to act in that respect is recognized by 
the Board; 
"artificial sources" means radiation sources other than natural 
radiation sources; 
"authorization" means a permission granted in a document by the 
Board application, or granted by national legislation, to carry out a 
practice or any other action within the scope of these regulations. 
Authorisation can take the form of a registration or a licence; 
"avertable dose" means the dose to be saved by a protective 
action; that is, the difference between the dose to be expected with 
the protective action and that to be expected without it; 
"Becquerel" (Bq): the special name of the unit of activity. One 
becquerel is equivalent to one decay per second; 
"Board" means the Radiation Protection Board; 
"calendar year" means a period of twelve calendar months 
beginning with the 1st January; 
"clearance levels" means values, established by the Board, and 
expressed in terms of activity concentrations and/or total activity, 
at or below which radioactive substances or materials containing 
radioactive substances arising from any practice subject to the 
requirement of notification or authorization may be released from 
the requirements of these regulations;

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 5 
"comforter and carer" means an individual who (other than as 
part of his occupation) knowingly and willingly incurs an exposure 
to ionizing radiation resulting from the support and comfort of 
another person who is undergoing or who has undergone any 
medical exposure; 
"committed effective dose" means the quantity E(t) defined as 
where HT(t ) is the committed equivalent dose to tissue T over the 
integration time t, and wT is the appropriate tissue weighting 
factor. When t is not specified, it will be taken to be 50 years for 
adults and to age 70 years for intakes by children. The unit for 
committed effective dose is the sievert. Committed effective dose 
could also be assessed using the committed effective dose per unitintake 
for ingested (h(g) j,ing) or inhaled (h(g) j,inh) radionuclide j 
gSv/Bqh by an individual in group of age g; J j,ing and J j,inh 
respectively are the relevant intakes via ingestion and inhalation of 
the radionuclide j gBqh; 
"committed equivalent dose" means the quantity HT(t) defined 
as: 
where t0 is the time of intake, HT(t) is the equivalent dose rate at 
time t in an organ or tissue, T and t is the time elapsed after an 
intake of radioactive substances. When t is not specified it will be 
taken to be 50 years for adults and to age 70 years for intakes by 
children. The unit for committed equivalent dose is the sievert; 
"controlled area" means any area in which specific protection 
measures and safety provisions are or could be required for 
controlling normal exposures or preventing the spread of 
contamination during normal working conditions and for 
preventing or limiting the extent of potential exposures, and to 
which access is controlled; 
"Convention" means the Convention on the Physical Protection 
of Nuclear Material; 
"critical group" means a group of members of the public which is 
reasonably homogeneous with respect to its exposure for a given 
radiation source and given exposure pathway and is typical of 
individuals receiving the highest effective dose or equivalent dose 
(as applicable) by the given exposure pathway from the given 
source; 
"deterministic effect" is a radiation effect for which generally 
exists a threshold of dose and above this threshold the severity of 
the effect increases with dose; 
"disposal" means the emplacement of waste in a repository, or a 
given location, without the intention of retrieval. Disposal also 
E(t ) = S wT.HT ( t   ) 
= S h(g) j,ing J j,ing + S h(g) j,inh J j,inh 
T J J 
ò 
t0+t 
HT(t) = HT(t)dt 
t0

6 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
c o v e r s t h e a p p r o v e d d i r e c t d i s c h a r g e o f w a s t e s i n t o t h e 
environment, with subsequent dispersion; 
"dose" means, in relation to ionizing radiation, any dose quantity 
or sum of dose quantities mentioned in the Third Schedule; 
"dose constraint" means a restriction on the prospective doses to 
individuals, which may result from a defined source for use at the 
planning stage in radiation protection whenever optimization is 
involved; 
"dose limit" means, in relation to persons of a specified class, the 
limit on effective dose or equivalent dose that shall not be 
exceeded; 
"effective dose" means the quantity E. defined as a summation of 
the tissue equivalent doses, each multiplied by the appropriate 
tissue weighting factor: 
where HT is the equivalent dose in tissue T and wT is the tissue 
weighting factor for tissue T. From the definition of equivalent 
dose, it follows that: 
where wR is the radiation weighting factor for radiation R and DT.R 
is the average absorbed dose in the organ or tissue T. The unit of 
effective dose is the sievert (Sv). Taking into consideration various 
pathways of exposure, the effective dose may consist of external 
exposure and committed effective dose: 
E = Eext + E(t) 
where Eext is the external dose; 
"emergency exposure" means an exposure of individuals 
implementing the necessary rapid action to bring help to 
endangered individuals, prevent exposure of a large number of 
people or save a valuable installation or goods, whereby one of the 
individual dose limits equal to that laid down for exposed workers 
could be exceeded. Emergency exposure shall apply only to 
volunteers; 
"emergency plan" means the set of procedures to be implemented 
in the event of a radiological accident. Emergency plans may be 
either on-site, that is for the whole area under the control of the 
radiation employer where a source is present or intended to be 
present, or off-site, that is the area beyond that under the control of 
the radiation employer; 
"equivalent dose'' means the quantity HT.R defined as: 
HT.R = DT.R.wR 
where DT.R is the absorbed dose delivered by radiation type R 
averaged over a tissue or organ T and wR is the radiation weighting 
E = S wT.HT 
T 
E = S wT. S wR. DT.R 
T R

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 7 
factor for radiation type R. 
When the radiation field is composed of different radiation types 
with different values of WR the equivalent dose is: 
The unit of equivalent dose is J/kg, termed the sievert (Sv); 
"exclusion" means the process whereby the Board deems that the 
magnitude or likelihood of an exposure is essentially unamenable 
to control and is thus excluded from regulatory control; 
"exemption" (from regulatory control, including those of 
notification, registration and licensing) refers to practices or work 
activities and sources within justified practices, for which the 
Board is satisfied that the sources comply with the exemption 
criteria specified in regulation 18 or such sources satisfy other 
exemption levels determined by the Board; 
"exposed workers" means persons, either self-employed or 
working for an employer, subject to an exposure incurred at work 
from practices and work activities covered by these regulations and 
liable to result in doses exceeding one or other of the dose levels 
equal to the dose limits for members of the public; 
"exposure" means the act or condition of being exposed to 
ionizing radiation. Exposure can be either external exposure 
(irradiation by sources outside the body) or internal exposure 
(irradiation by sources inside the body). Exposure can be classified 
a s e i t h e r n o r m a l e x p o s u r e o r p o t e n t i a l e x p o s u r e ; e i t h e r 
occupational, medical or public exposure: and, in intervention 
situations, either emergency exposure or chronic exposure. The 
term exposure is also used in radiodosimetry to express the amount 
of ionization produced in air by ionizing radiation; 
"external employer" means any person, other than the radiation 
employer, and including members of the staff of the external 
employer, performing services of any sort in a controlled area; 
"Gray" (Gy) means the name of the unit of absorbed dose. One 
gray is equal to one joule per kilogram: 
1 Gy = 1 J kg-1; 
"health detriment" means an estimate of the risk at reduction in 
length and quality of life occurring in a population following 
exposure to ionizing radiation. This includes loss arising from 
somatic effects, cancer and severe genetic disorder; 
"health record" means, in relation to a worker, the record of 
medical surveillance of that worker maintained by the employer in 
accordance with regulation 45; 
"intake" means the process of taking radionuclides into the body 
by inhalation or ingestion or through the skin; 
"international nuclear transport" means the carriage of a 
consignment of nuclear material by any means of transportation 
intended to go beyond the territory of the State where the shipment 
HT = S wR. DT.R 
R

8 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
originates beginning with the departure from a facility of the 
shipper in that State and ending with the arrival at a facility of the 
receiver within the State of ultimate destination; 
"intervention" means a human activity that prevents or decreases 
the exposure of individuals to radiation from sources which are not 
part of a practice and work activity or which are out of control, by 
acting on sources, transmission pathways and individuals 
themselves; 
"intervention level" means a value of avertable equivalent dose, 
avertable effective dose or a derived value, at which intervention 
measures should be considered. The avertable dose or derived 
value is solely that associated with the exposure pathway to which 
the intervention measure is to be applied; 
"ionizing radiation" means the transfer of energy in the form of 
particles or electromagnetic waves of a wavelength of 100 
nanometers or less or a frequency of 3 X 1015 Hertz or more 
capable of producing ion pairs in biological materials; 
"local rules" means rules made in accordance with regulation 36; 
"maintained", where the reference is to maintaining plant, 
apparatus, equipment or facilities, means maintained in an efficient 
state, in efficient working order and good repairs; 
Cap. 234. 
"Maltese ship'' shall have the same meaning as is assigned to it 
by article 3 of the Merchant Shipping Act; 
"medical exposure" means exposure incurred by - 
(a) patients as part of their own medical or dental 
diagnosis or treatment; 
(b) persons knowingly and voluntarily helping (other than 
those occupationally exposed), in the support and 
comfort of patients undergoing medical diagnosis and 
treatment; and 
(c) volunteers in a programme of biomedical research 
involving their exposure; 
"member of the public" means in a general sense, any individual 
in the population except, for the purposes of these regulations, 
when subject to occupational or medical exposure, and for the 
purpose of verifying compliance with the annual dose limit for 
public exposure, shall mean the representative individual in the 
relevant critical group; 
"Minister" means the Ministers responsible for occupational 
health and safety, for the environment, for health or for internal 
affairs, acting together or separately as appropriate; 
"natural radiation sources" mean sources of ionizing radiation 
from natural terrestrial or cosmic origin; 
"normal exposure" means an exposure that is expected to be 
received under normal operating conditions of an installation or a 
source, including possible minor mishaps that can be maintained 
under control; 
"notification" means the requirement of submitting a document

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 9 
to the Board to notify the intention to carry out a practice or work 
activity or any other action within the scope of these regulations; 
"nuclear material" means plutonium except that with isotopic 
concentration exceeding 80% in plutonium-238; uranium-233; 
uranium enriched in the isotope 235 or 233; uranium containing the 
mixture of isotopes as occurring in nature other than in the form of 
ore or ore-residue; any material containing one or more of the 
foregoing; 
"occupational exposure" consists of all exposures of workers 
incurred in the course of their work, with the exception of 
exposures excluded from these regulations and exposures from 
practices and work activities or sources exempted by these 
regulations; 
"outside worker" means a category A person (including trainees, 
apprentices or students over 18 years) who carries out services in 
the controlled area of any employer (other than the controlled area 
of his own employer), whether employed temporarily, permanently, 
or as a self-employed person; 
"person" includes a body of persons and any body corporate 
established by or under any law; 
"potential exposure" means exposure, that is not expected to be 
delivered with certainty, with a probability of occurrence that can 
be estimated in advance, that may result from an accident at a 
source or owing to an event or sequence of events of a probabilistic 
nature, including equipment failures and operating errors; 
"practice" means any human activity action that can increase the 
exposure of individuals to radiation, or extend exposure or the 
likelihood of exposure to additional people from an artificial 
source, or from a natural radiation source where natural 
radionuclides are processed for their radioactive, fissile or fertile 
properties, except in the case of an emergency exposure; 
"public exposure" means an exposure incurred by members of 
the public from radiation sources, excluding any occupational or 
medical exposure as well as the radiation from the local 
undisturbed background, but including exposure from authorised 
sources, practices and from intervention situations; 
"qualified expert" means a person having the knowledge and 
training needed to carry out physical, technical or radiochemical 
tests enabling doses to be assessed, and to give advice in order to 
ensure effective protection of individuals and the correct operation 
of protective equipment, and whose capacity to act as a qualified 
expert is recognized by the Board. A qualified expert may be 
assigned the technical responsibility for the tasks of radiation 
protection of workers and members of the public; 
Cap. 424. 
"radiation employer" shall have the same meaning as is assigned 
to the word "employer" by article 2 of the Occupational Health and 
Safety Authority Act and includes: 
(a) any natural or legal person who carries out the 
practices or work activities referred to in regulation 4 
and, for the purposes of regulations 17 and 19,

10 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
includes a person who intends to carry out such work 
and who has the legal responsibility under national law 
for such practices or work activities; and 
(b) any duty imposed by these regulations on an employer 
in respect of his worker shall extend to a selfemployed 
person in respect of himself; 
"radiation passbook" means - 
(a) in the case of a worker employed by an employer in 
Malta a passbook approved by the Board for the 
purpose of these regulations; 
(b) in the case of an outside worker employed by an 
employer in an EU member State, a passbook 
authorised by the competent authority for that member 
State, as the case may be; 
"radiation weighting factor" (wR) is a dimensionless factor used 
to weight the dose absorbed in tissue according to the type of 
radiation; 
"radiation worker" is any person who works, whether full or part 
time or temporarily, for an employer who has recognised rights and 
duties in relation to occupational radiation protection; 
"radioactive contamination" means the presence of radioactive 
substances in or on any material, surface (including any surface of 
the body or clothing) or environment, including liquids or gases, or 
the human body where they are undesirable or could be harmful. In 
the specific case of the human body, this radioactive contamination 
i n c l u d e s b o t h e x t e r n a l s k i n c o n t a m i n a t i o n a n d i n t e r n a l 
contamination, irrespective of route of intake; 
"radioactive substance" means any substance that contains one or 
more radionuclides the activity or concentration of which cannot be 
disregarded as far as radiation protection is concerned; 
"radiological emergency" means a situation that requires urgent 
action in order to protect workers, members of the public or the 
population either partially or as a whole; 
"radioactive waste" means a material of whatever physical form, 
remaining from practices and work activities or interventions, for 
which no further use is foreseen at present and which (i) contains or 
is contaminated with radioactive substances having activity or 
activity concentration higher than the relevant level of exemption 
from regulatory control, and (ii) exposure to which is not excluded 
from these regulations; 
Cap. 234. 
"Registrar-General" shall have the same meaning as is assigned 
to it by article 2 of the Merchant Shipping Act; 
"regulatory authority" means the Radiation Protection Board, 
jointly set up by the below mentioned members, which exercise 
their respective regulatory functions in the area of nuclear safety 
and radiation protection through the Board: 
Cap. 424. 
(1) the Occupational Health and Safety Authority set up in 
terms of the Occupational Health and Safety Authority 
Act as regards the protection of workers from exposure

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 11 
to radiation sources at work; 
Cap. 435. 
(2) the Environment Protection Directorate or other 
competent authority as established by virtue of article 
6 of the Environment Protection Act, as regards 
protection of the environment from radiation sources; 
Cap. 94. 
(3) the Superintendent of Public Health in terms of the 
Department of Health (Constitution) Ordinance, in 
matters relating to the protection of the general 
population from radiation sources; 
Cap. 411. 
(4) the Civil Protection Department established by the 
Civil Protection Act in relation to preparation for and 
response to civil emergencies; 
(5) any other authority which, in the opinion of the Prime 
Minister, after consultation with the Board, may have 
a regulatory function in the field of ionizing radiation; 
(6) any other authority to which the Ministers responsible 
for occupational health and safety, civil protection, 
health or the environment may, from time to time, 
assign any of the responsibilities of the abovementioned 
under these regulations: 
Provided that the Prime Minister shall issue a notice of any 
such assignment of responsibilities in the Gazette; 
"sealed source" means a source containing any radioactive 
substance that is permanently sealed in a capsule or closely 
bounded and in a solid form; and the capsule or material of which is 
strong enough to maintain leaktightness under the conditions of use 
and wear for which the source was designed as well as in cases of 
foreseeable mishaps; 
"Sievert" means the name of the unit of equivalent or effective 
dose. One sievert is equivalent to one joule per kilogram: 
1 Sv = 1 J kg-1; 
"stochastic effects" of radiation are radiation effects which 
generally occur without a threshold level of dose and whose 
probability of occurring is proportional to the dose magnitude, 
whereas the severity of effects is independent of dose; 
"source" means an apparatus, a radioactive substance or an 
installation capable of emitting ionizing radiation or radioactive 
substances; 
"supervised area" means an area subject to appropriate 
supervision for the purpose of protection against ionizing radiation 
and which has been so designated by the employer in accordance 
with regulation 35; 
"tissue weighting factor" (wT) is a dimensionless factor used to 
weight the equivalent dose in a tissue T; 
"trainee" means a person aged 16 years or over (including a 
student) who is undergoing instruction or training which involves 
operations which would, in the case of a worker, be work with 
ionising radiation;

12 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
"transport" means, in relation to a radioactive substance, carriage 
of that substance on a road or through another public place 
(whether on a conveyance or not), or by rail, inland waterway, sea 
or air and, in the case of transport on a conveyance, a substance 
shall be deemed as being transported from the time that it is loaded 
onto the conveyance for the purpose of transporting it until it is 
unloaded from that conveyance, but a substance shall not be 
considered as beings transported if - 
(a) it is transported by means of a pipeline or similar 
means; or 
(b) it forms an integral part of a conveyance and is used in 
connection with the operation of that conveyance; 
"uranium enriched in the isotope 235 or 233" means uranium 
containing the isotope 235 or 233 or both in an amount such that 
the abundance ratio of the sum of these isotopes to the isotope 238 
is greater than the ratio of the isotope 235 to the isotope 238 
occurring in nature; 
Cap. 424. 
"work'' shall have the same meaning as is assigned to it by article 
2 of the Occupational Health and Safety Authority Act and shall 
include any instruction or training which a person undergoes as a 
trainee and the meaning of "at work" shall be considered 
accordingly; 
"work activity" means a sequence of man-made actions, 
involving naturally occurring radionuclides, which are not aimed at 
processing and, or extracting these radionuclides for their 
radioactive, fissile or fertile properties; 
Cap. 424. 
"worker" shall have the same meaning as is assigned to it by 
article 2 of the Occupational Health and Safety Authority Act. 
Application. 4. (1) These regulations shall apply to all practices and work 
activities which involve a risk from ionizing radiation emanating 
from an artificial source or from a natural radiation source in cases 
where natural radionuclides are or have been processed in view of 
their radioactive, fissile or fertile properties, namely: 
(a) the production, processing, handling, use, holding, 
storage, transport, supply, import to and export from 
Malta, transit through Maltese territory and disposal of 
radioactive substances; 
(b) the operation of any electrical equipment emitting 
ionizing radiation and containing components 
operating at a potential difference of more than 5 kV: 
(c) discontinuance or cessation of a practice or work 
activity involving radioactive substances and devices 
that produce radiation and are used for industrial, 
medical, agricultural, research and education 
purposes; 
(d) any other practice or work activity specified from time 
to time by the Board. 
(2) In accordance with Part II, these regulations shall apply to 
nuclear material used for peaceful purposes while in international

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 13 
nuclear transport, and as applicable to domestic use, storage and 
transport. 
(3) In accordance with Part XII they shall also apply to work 
activities which are not covered by subregulation (1) but which 
involve the presence of natural radiation sources and may lead to a 
significant increase in the exposure of workers or members of the 
public which cannot be disregarded from the radiation protection 
point of view. 
(4) In accordance with Part XIV it shall also apply to any 
intervention in cases of radiological emergencies or in cases of 
lasting exposure resulting from the after-effects of a radiological 
emergency or a past or old practice or work activity. 
(5) These regulations shall not apply to exposures associated 
with excluded or exempted situations. 
PART II 
PHYSICAL PROTECTION OF NUCLEAR MATERIAL 
Text of 
Convention. 
5. For the purpose of article 3(4) of the Act, the text of the 
Convention, which these regulations shall implement, is being 
published in the Sixth Schedule. 
Physical protection 
requirements for 
the import into, 
transit through or 
export from 
Maltese territory of 
nuclear material. 
6. (1) No person shall, wIth regards to nuclear material - 
(a) export or authorize the export of such material from 
Malta; 
(b) import or authorize the import of such material into 
Malta; 
(c) transit Maltese territory by land or through its airports 
or seaports, 
unless prior authorisation has been granted by the Board, acting in 
close co-ordination with the Malta Maritime Authority and the 
Department of Civil Aviation, which may stipulate any conditions 
and levy any charges in this regard. 
(2) The Board shall not grant authorisations for - 
(a) importation of nuclear material from, or transit 
through Maltese territory of such material en route to, 
States which are not party to the Convention, or 
(b) the export of such material from Malta, 
unless the Board receives assurances that such material will be 
protected at the levels described in Annex I of the Sixth Schedule 
during the international nuclear transport and is supplied with all 
relevant information to enable it to inform in advance the States 
which the nuclear material is expected to transit by land or internal 
waterways or whose airports and seaports it is expected to enter. 
International 
nuclear transport 
by Maltese ships 
and aircraft. 
7. (1) No Maltese ship or aircraft shall carry nuclear material 
unless such material is protected at the levels described in Annex I 
of the Sixth Schedule during international nuclear transport. 
(2) It shall be the duty of the commander in the case of a 
Maltese aircraft, to ensure that there is prior authorisation for the

14 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
transport of nuclear material from the competent authorities of the 
exporting and importing states, after giving the necessary 
assurances and satisfying any conditions in this regard. 
(3) It shall be the duty of the master, in the case of a Maltese 
ship, to ensure that there is prior authorisation for international 
nuclear transport from the Registrar-General, after giving the 
necessary assurances and satisfying any conditions in this regard: 
Provided that the Registrar-General may stipulate any 
conditions and levy any charges in relation to such authorisations, 
and it shall be the duty of the master to ensure that these conditions 
are at all times adhered to. 
Prohibition of 
activities in 
relation to nuclear 
material. 
8. No person shall intentionally commit - 
(a) an act without lawful authority which constitutes the 
receipt, possession, use, transfer, alteration, disposal 
or dispersal of nuclear material and which causes or is 
likely to cause death or serious injury to any person or 
substantial damage to property; 
(b) a theft or robbery of nuclear material; 
(c) an embezzlement or fraudulent obtaining of nuclear 
material; 
(d) an act constituting a demand for nuclear material by 
threat or use of force or by any other form of 
intimidation; 
(e) a threat - 
(i) to use nuclear material to cause death or serious 
injury to any person or substantial property 
damage, or 
(ii) to commit an offence described in paragraph (b) 
in order to compel a natural or legal person, 
international organization or State to do or to 
refrain from doing any act; 
(f) an attempt to commit any offence described in 
paragraphs (a), (b) or (c); and 
(g) an act which constitutes participation in any offence 
described in paragraphs (a) to (f). 
PART III 
RADIATION PROTECTION BOARD 
Functions and 
responsibilities. 
9. (1) There shall be set up a Radiation Protection Board, 
hereinafter referred to as the Board, which shall act as the 
regulatory authority in the field of nuclear safety and radiation 
protection. 
(2) The Board shall have such functions as may devolve on it 
under any other law or as may be assigned to it in writing by the 
Prime Minister or by the member agencies represented on the 
Board. In the case that other regulations are in force governing 
occupational, public, and medical exposures, or environmental 
protection and safety of sources, which in some way address the

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 15 
use of ionizing radiation, the Board shall, if it considers it 
necessary, make recommendations to the Prime Minister for the 
reallocation of the regulatory responsibility to the Board itself or to 
some other authority as the Board deems fit. 
(3) It shall be the function of the Board to: 
(a) take the necessary measures to improve the cooperation 
and co-ordination of the government bodies 
which have responsibility for issues related to 
occupational health and safety, environment, public 
health and civil protection amongst themselves and 
with other interested parties; 
(b) tender advice to the Prime Minister on allocation of 
responsibilities in the field of nuclear safety and 
radiation protection when these are unclear or 
unresolved; 
(c) co-ordinate the preparation of regulations governing 
notification, authorization of practices, work 
activities, radiation sources and establishing radiation 
protection and safety requirements; 
(d) define exposures that are excluded from regulatory 
requirements on the basis of their being unamenable to 
regulatory control; 
(e) receive notifications, and issue authorisations and 
grant exemptions concerning the possession and use of 
radiation sources, subject to any condition that may be 
required in the opinion of the Board and to revoke at 
any time any such authorisations if the Board feels that 
the required standards or levels of safety are not being 
complied with; 
(f) co-ordinate and conduct inspections and enforcement 
actions to assess radiation safety conditions and 
compliance with applicable regulatory and 
authorisation requirements and to protect the health 
and safety of workers and the public; 
(g) compile a national register of practices, work activities 
and sources; 
Cap. 424. 
(h) authorise persons to carry out inspections and to take 
such action on its behalf on particular issues of 
regulatory interest and such persons shall be construed 
as being officers as per Part IV of the Occupational 
Health and Safety Authority Act; 
(i) set up and run a National Interim Storage Facility for 
orphan and disused radioactive sources; 
(j) gather the required data to enable an assessment of 
total exposure from all practices and work activities in 
Malta and including the distribution of the individual 
occupational and public exposures for each type of 
practice, and to enable the setting up of a National 
Register for Occupational Exposure to Ionising 
Radiation;

16 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(k) initiate surveys on background radiation and 
radioactive contamination of all environmental media; 
(l) approve the capacity of persons to act as approved 
dosimetric services and qualified experts subject to the 
provisions of regulation 11; 
(m) establish guidance on protective measures required in 
controlled and supervised areas; 
(n) make recommendations, or provide technical advice 
on intervention and emergency responses, as 
appropriate; 
(o) advise other governmental authorities and other 
persons on matters within the competence of the 
Board; 
(p) promote or carry out research on radiation safety 
issues of regulatory concern; 
(q) maintain contact for information exchange and 
cooperation in any field related to nuclear safety and 
radiation protection with regulatory bodies of other 
countries and relevant international organizations; 
(r) establish appropriate mechanisms to inform the public 
about the regulatory process and the radiation safety 
aspects of regulated practices and work activities; 
(s) coordinate the establishment of technical standards, 
preparation of Codes of Practice and other guidance 
documents by the relevant authorities; 
(t) appropriate1v investigate any accident or incident 
involving radiation sources at a practice or work 
activity; 
(u) be the national body which gives effect to any decision 
of the UN Security Council or International Atomic 
Energy Agency, or other internationally recognised 
entity or competent authority in the field of nuclear 
safety and radiation protection whenever so directed 
by the Prime Minister; 
(v) to identify organisations, which may need to be 
involved in emergency situations and relevant 
intervention and define their responsibilities; and 
(w) take on any other additional activities in the field of 
radiation protection which the member agencies 
comprising the Board may, from time to time, pass on 
to the Board. 
(4) Any decisions taken by the Board in respect of anything 
related to a notification, authorisation or exemption of practices, 
work activities, and sources, as well as in respect of any other of its 
functions, shall be considered to have been taken on behalf, and 
with the full powers, of the member agencies represented on the 
Board. Any document pertaining to any such decisions shall be 
signed by the Executive Chairperson. 
(5) A person who feels aggrieved by any decisions taken by the

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 17 
Board, shall have the right to ask the Board to reconsider such 
decisions, citing reasons for requesting a reconsideration. 
Composition of the 
Board. 
10. (1) The Prime Minister shall appoint officers of the 
member agencies to serve as expert members on the Board. The 
Board shall be composed as follows: 
(a) one member representing the Occupational Health and 
Safety Authority; 
(b) one member representing the Environment Protection 
Directorate; 
(c) one member representing the Superintendent of Public 
Health; 
(d) one member representing the Civil Protection 
Department. 
(2) The Occupational Health and Safety Authority shall also 
appoint a technically competent person to act as Executive 
Chairperson to the Board, who shall be responsible for the 
organization of the work of the Board. 
(3) Each member shall hold office for a period of three years, 
and the members so appointed may be re-appointed on the expiry of 
their term: 
Provided that they shall remain in office on completion of 
their term, until the Prime Minister formally informs them of the 
appointment of a substitute. 
(4) A member of the Board may, by notice in writing addressed 
to the Prime Minister, resign his membership. 
(5) The Prime Minister may remove a member of the Board 
from office if, in the opinion of the Prime Minister, such member is 
unfit to continue in office or has become incapable of properly 
performing his duties as a member. 
(6) The Board shall meet as often as necessary to discharge its 
functions, either at the request of the Executive Chairperson or at 
the request of any other two members representing different 
member agencies. 
(7) Three persons attending a meeting shall constitute a 
quorum. The Executive Chairperson shall, in the event of a tie in 
voting, have both an initial vote as well as a casting vote: 
Provided that without prejudice to the preceding 
subregulation, the Board shall regulate its own procedures. 
(8) It shall be the joint duty of the member agencies 
constituting the Board to ensure that the overall functions of the 
Board are carried out in close collaboration and as efficiently as 
possible, and the Occupational Health and Safety Authority shall 
take the lead in co-ordinating the administrative actions of the 
Board. 
Approval of 
services. 
11. (1) The Board (or such other person as may from time to 
time be specified in writing by it) may, by a certificate in writing, 
approve (in accordance with such criteria as may from time to time

18 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
be specified by the Occupational Health and Safety Authority) - 
- the approved medical practitioners; 
- the approved occupational health services, 
for such of the purposes of these regulations as are specified in the 
certificate. 
(2) The Board may, by a certificate in writing, approve - 
- the approved dosimetric services, 
- the qualified experts, 
for such of the purposes of these regulations as are specified in the 
certificate. 
(3) A certificate made pursuant to subregulations (1) and (2) 
may be made subject to conditions and may be revoked in writing 
at any time. 
(4) Any approval granted pursuant to subregulations (1) and (2) 
may be reassessed at such suitable periods as considered 
appropriate by the issuing body. 
Funding for Board. 12. (1) The Occupational Health and Safety Authority shall 
ensure sufficient funding to enable the Board to fulfil its 
obligations. This shall be ensured irrespective of any funds 
obtained pursuant to subregulation (2). 
(2) The Board may charge any person a fee for performing any 
of its functions under these regulations, and such a fee may include 
provision for costs incurred in the event of inability of the radiation 
employer to return disused sources to the manufacturer, and such 
fees shall be made payable to the Occupational Health and Safety 
Authority. 
(3) When the Board requests payment, the fee due, which shall 
be recoverable only as a civil debt, shall become payable one 
month after a statement to that effect has been sent or given. 
Advisory 
committees. 
13. The Board shall be entitled to engage persons to serve as 
individual expert advisers or to set up advisory committees and 
appoint members to serve on such advisory committees as may be 
useful and appropriate for the Board to enable it to better discharge 
its responsibilities. 
Address of Board. 14. The offices of the Board shall be at any address that the 
Board may occupy, provided that this has been notified in the 
Gazette. All correspondence should be addressed to the Executive 
Chairperson of the Board. 
Cooperation with 
other Maltese 
authorities. 
15. The Board shall establish a permanent mechanism for 
exchange of information and cooperation with any relevant Maltese 
authority as it considers necessary in the fulfilment of its duties, 
including but not limited to: 
(a) the Customs authorities, to ensure adequate control, 
including, as appropriate, prior notification of, or 
authorisation by, the Board, over sources entering and 
leaving the country and the proper identification and

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 19 
authorization of the persons importing or receiving the 
sources; 
(b) the Ministry for Transport to ensure that adequate 
levels of safety are maintained during the storage and 
transport of radioactive material, whether on Maltese 
territory or on ships or aircraft under Maltese 
jurisdiction. 
Powers of Prime 
Minister in relation 
to Board. 
16. The Prime Minister may, after consultation with the other 
relevant authorities - 
(a) confer on the Board any new functions for purposes 
connected with the protection from radiation hazards, 
(b) terminate any function of the Board made under these 
regulations. 
PART IV 
NOTIFICATION AND AUTHORISATION 
Notification. 17. (1) Any person who intends to - 
(i) adopt or introduce, conduct, discontinue or cease 
to operate a practice or work activity involving 
the use of ionising radiation, as well as 
(ii) design, manufacture, construct or assemble, 
acquire, import or export, distribute, sell, loan or 
hire, possess, locate, commission, use and 
operate, maintain or repair, transfer or 
decommission, disassemble, transport, store or 
dispose of radioactive material, as applicable, 
within a practice or work activity, 
shall, at least thirty days before doing so: 
(a) submit to the Board a formal written notification of the 
intention to do so giving all information listed in the 
First Schedule and any other information which may 
from time to time be required by the Board, and 
(b) if appropriate, in accordance with the requirements 
established by the Board, also submit to the Board a 
request for formal written authorisation pursuant to 
regulation 19 from the Board to do so: 
Provided that the Board may exclude the exposure from 
such a practice, work activity or source, or exempt the practice, 
work activity or the source from the requirements of these 
regulations, including the requirements of notification and 
authorization. 
(2) The requirement to submit appropriate notification and 
request authorisation pursuant to subregulation (1) shall also apply 
to practices and work activities already in operation on the date of 
entry into force of these regulations, but in such cases these 
practices and work activities shall have six months to perform the 
notification or request authorisation pursuant to regulation 19, as 
appropriate. 
(3) Where a radiation employer has notified a practice or work

20 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
activity in accordance with subregulation (2), the Board may, by 
notice in writing served on him, require that radiation employer to 
provide such additional particulars of that work as it may 
reasonably require, and in such a case the radiation employer shall 
provide those particulars by such time as is specified in the notice 
or by such other time as the Board may subsequently agree. 
(4) The radiation employer shall submit to the Board, for its 
examination and approval, all relevant information about the 
practice or work activity which may be considered necessary by the 
Board and which shall include: 
(a) plans for installations involving an exposure risk, 
expressed in safety assessment, and of the proposed 
siting, design and operation of such installations 
within the territory concerned, from the point of view 
of radiation protection; 
(b) adequacy of the protection measures to be adopted, 
before acceptance into service approval of operation of 
new installations is given, against any radiation 
exposure or radioactive contamination liable to extend 
beyond the perimeter, taking into account, if relevant. 
demographic, meteorological, geological, hydrological 
and ecological conditions. 
(5) Where a radiation employer has notified work in 
accordance with subregulation (2) and subsequently makes a 
material change in that work which would affect the particulars so 
notified, he shall forthwith notify the Board of that change and 
request new authorisation. 
Exclusions and 
exemptions from 
requirement to 
perform 
notification. 
18. (1) Exposures from natural radioactivity in the body, from 
cosmic radiation on Earth’s surface, unmodified concentrations of 
natural radionuclides in raw materials and any other sources that 
are essentially unamenable to control, as may be determined by the 
Board, are excluded from the requirements of these regulations. 
(2) The requirement to notify the Board of the intention to 
carry out a practice or work activity pursuant to regulation 17 shall 
not apply to the following: 
(a) radioactive substances contained in a material having 
mass of 1 tonne or less, where the concentration of 
activity per unit mass, of a given radionuclide, at any 
one time, do not exceed the exemption values set out 
in column 2 of Table A of the Second Schedule or, in 
exceptional circumstances different values authorized 
by the Board that nevertheless satisfy the basic general 
criteria set out in the Second Schedule; or 
(b) radioactive substances contained in a material having 
mass of 1 tonne or less, where the quantities involved 
do not exceed in total (for the same radionuclide), at 
any one time, the exemption values set out in column 3 
of Table A of the Second Schedule or, in exceptional 
circumstances different values authorized by the Board 
that nevertheless satisfy the basic general criteria set

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 21 
out in the Second Schedule; or 
(c) apparatus containing radioactive substances exceeding 
the quantities or concentration values specified in 
paragraphs (a) or (b), provided that: 
(i) it is of a type approved by the Board; and 
(ii) it is constructed in the form of a sealed source; 
and 
(iii) it does not cause, in normal operating 
conditions, a dose rate exceeding 1 µSv h-1 at a 
distance of 0.1 m from an accessible surface of 
the apparatus, nor a dose to any member of the 
public exceeding 10 µSv h -1 and 
(iv) conditions for disposal have been specified by 
the Board; or 
(d) the operation of any electrical apparatus to which these 
regulations apply, other than that referred to in 
paragraph (e), provided that: 
(i) it is of a type approved by the Board; and 
(ii) it does not cause, in normal operating 
conditions, a dose rate exceedingþ 1 µSv h-1 at a 
distance of 0.1 m from any accessible surface of 
the apparatus, nor a dose to any member of the 
public exceeding 10 µSv h -1; or 
(e) the operation of any cathode ray tube intended for the 
display of visual images, or other electrical apparatus 
operating at a potential difference not exceeding 30 
kV, provided that this operation does not cause, in 
normal operating conditions, a dose rate exceeding 1 
µSv h-1 at a distance of 0.1 m from any accessible 
surface of the apparatus, nor a dose to any member of 
the public exceeding 10 µSv h-1; or 
(f) radioactive or radioactively contaminated material, 
which is subject to a valid exemption or unconditional 
clearance issued by the Board. 
Authorisation. 19. (1) Unless exempted by regulation 18, it shall be the duty 
of the radiation employer, to submit a request for authorisation to 
the Board and to obtain written authorisation from the Board to 
operate a practice or work activity prior to commencement of any 
activity relating to or involving the emission of ionising radiation 
and/or generation of radioactive residues or waste, or discharge of 
radioactive substances into the environment in any of the following 
practices or work activities: 
(a) operation and decommissioning of any facility of the 
nuclear fuel cycle and exploitation and closure of 
uranium mining; 
(b) the deliberate addition of radioactive substances in the 
production and manufacture of medicinal products and 
the import or export of such goods; 
(c) the deliberate addition of radioactive substances in the

22 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
production and manufacture of goods and the import 
or export of such goods; 
(d) the deliberate administration of radioactive substances 
to persons and, in so far as radiation protection of 
human beings is concerned. animals for the purpose of 
medical or veterinary diagnosis, treatment or research; 
(e) the use of X-ray sets or radioactive sources for - 
• industrial radiography or 
• processing of products or 
• research or 
• education or 
• the exposure of persons for medical diagnosis or 
treatment and 
• the use of accelerators except electron 
microscopes; 
(f) where an authorisation has been granted pursuant to 
subregulation (1) and the radiation employer, to whom 
the authorisation was granted, subsequently makes a 
material or operational change to the circumstances 
relating to that authorisation; 
(g) any other practice or work activity for which the Board 
may from time to time decide that authorisation is 
required: 
Provided that the Board may specify that a practice or work 
activity shall not require authorisation where the practice or work 
activity has been exempted from notification by the Board. 
(2) An authorisation granted under subregulation (1) may be 
granted subject to conditions and with or without limit of time and 
may be revoked in writing at any time. 
(3) Where an authorisation has been granted pursuant to 
subregulation (1) and the radiation employer to whom the 
authorisation was granted subsequently makes a material change to 
the circumstances relating to that authorisation, that change shall 
forthwith be notified to the Board by the radiation employer. 
(4) It shall be the duty of the radiation employer to obtain prior 
authorisation from the Board for the disposal, recycling or reuse of 
radioactive substances or materials containing radioactive 
substances arising from any practice or work activity subject to the 
requirement of notification or authorisation: 
Provided that the Board may release the disposal, recycling 
or reuse of such substances or materials from the requirements of 
these regulations provided they comply with clearance levels to be 
set by the Board: 
Provided further that these clearance levels shall take into 
account the basic exemption criteria to be established by the Board 
on its behalf and shall not be higher than the levels set out in the 
Second Schedule unless otherwise approved by the Board. 
PART V

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 23 
JUSTIFICATION, OPTIMIZATION AND DOSE LIMITATION 
FOR PRACTICES OR WORK ACTIVITIES 
Justification and 
optimisation. 
20. (1) It shall be the duty of the radiation employer to ensure 
that all new classes or types of practice resulting in exposure to 
ionizing radiation are justified, prior to being first adopted or first 
approved, taking into account their economic, social or other 
benefits in relation to the health detriment they may cause. 
(2) The radiation employer shall review the justification of 
existing practices or work activities or types of practice whenever 
new and important evidence about their efficacy or consequences is 
acquired. 
(3) In addition, the radiation employer shall ensure that: 
(a) in relation to exposures from any source within a 
practice or work activity, protection and safety shall be 
optimized in order that the magnitude of individual 
doses, the number of people exposed and the 
likelihood of incurring exposures all be kept as low as 
reasonably achievable, economic and social factors 
being taken into account, within the restriction that the 
doses to individuals delivered by the source be subject 
to dose constraints; 
(b) without prejudice to regulation 23, the sum of the 
doses from all relevant practices or work activities 
shall not exceed the dose limits laid down in these 
regulations for exposed worker, apprentices and 
students and members of the public: 
Provided that paragraph (b) shall not apply to: 
(a) medical exposures of individuals as part of their own 
medical diagnosis or treatment, 
(b) to exposures of comforters and carers and 
(c) to exposures of volunteers participating in medical and 
associated research programmes. 
(4) The radiation employer shall ensure that the process of 
optimization of protection and safety measures, which may range 
from intuitive qualitative analyses to quantitative analyses using 
decision aiding techniques, shall be sufficient to take all relevant 
factors into account in a coherent way so as to contribute to 
achieving the following objectives: 
(a) to determine optimized protection and safety measures 
for the prevailing circumstances, with account being 
taken of the available protection and safety options as 
well as the nature, magnitude and likelihood of 
exposures; and 
(b) to establish criteria, on the basis of the results of the 
optimization, for the restriction of the magnitudes of 
exposures and of their probabilities by means of 
measures for preventing accidents and mitigating their 
consequences. 
(5) The principle set out in subregulation (3)(a) shall apply to

24 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
all exposures to ionizing radiation resulting from the practices or 
work activities referred to in regulation 4 (1). 
Dose constraints. 21. (1) The radiation employer shall ensure that, except for 
medical exposure, the optimization of the protection and safety 
measures associated with any particular source within a single 
practice or work activity shall be subject to dose constraints. The 
magnitude of the generic dose constraint set by the Board is given 
in the Third Schedule. 
(2) The Board may establish guidance, which may include dose 
constraints, on the appropriate procedures to be applied to 
individuals who are comforters and carers or who are participating 
in medical and biomedical research programmes. 
Dose limitation. 22. (1) Every radiation employer shall ensure that the normal 
exposure of individuals shall be restricted so that neither the total 
effective dose nor the total equivalent dose to relevant organs or 
tissues, caused by the possible combination of exposures from 
ionising radiation from all relevant practices or work activities, 
exceeds the relevant dose limit specified in the Third Schedule for 
such class of person in any calendar year, except in special 
circumstances provided for in regulation 23. 
(2) Dose limits shall not apply to doses incurred by undisturbed 
local background and to medical exposures from authorized 
practices. 
(3) Where there is reasonable cause to believe that any worker 
has been exposed to an effective dose greater than 20 mSv in any 
calendar year, the employer shall, as soon as is practicable: 
(a) undertake an investigation into the circumstances of 
the exposure for the purpose of determining whether 
the dose limit referred to in the appropriate class in the 
Third Schedule is likely to be complied with; and 
(b) notify the Board of that suspected exposure. 
Specially 
authorised 
exposures. 
23. (1) In exceptional circumstances, excluding radiological 
emergencies and evaluated case by case, the Board, may, where 
some specific operation so requires, authorize individual 
occupational exposures of some identified workers exceeding the 
dose limits set out in the Third Schedule, provided that such 
exposures are - 
(i) limited in time, 
(ii) confined to certain working areas and; 
(iii) within maximum exposure levels defined for the 
particular case by the Board. 
(2) Any authorisations granted pursuant to subregulation (1) 
shall take the following into account: 
(a) only category A workers as defined in regulation 28, 
and who volunteer to do so, may be subject to 
specially authorized exposures; 
(b) apprentices, students, pregnant women and

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 25 
breastfeeding women who are likely to be bodily 
contaminated shall be excluded from such exposures; 
(c) the radiation employer shall carefully justify these 
exposures in advance and thoroughly discuss them 
with the voluntary workers, their representatives, the 
approved occupational health service or the qualified 
expert; 
(d) information about the risks involved and the 
precautions to be taken during the operation shall be 
provided to the relevant workers in advance; 
(e) all doses relating to such exposures shall be separately 
recorded in the individual dose record referred to in 
regulation 38 and the health record referred to in 
regulation 45. 
(3) The exceeding of dose limits as a result of specially 
authorized exposures shall not necessarily constitute a reason by 
the employer for excluding from his usual occupation or relocating 
the worker, without the agreement of the worker. 
(4) Protection of workers undertaking an intervention is 
specified in the Seventh Schedule. 
Exposure of the 
population as a 
whole. 
24. (1) Each radiation employer shall take reasonable steps to 
ensure that the contribution to the exposure of the population aa a 
whole from a practice or work activity is kept as low as reasonably 
achievable, economic and social factors being taken into account. 
(2) The Board, on behalf of the Superintendent of Public 
Health, shall take the necessary initiatives to ensure that the total of 
all such contributions shall be regularly assessed. 
PART VI 
ESTIMATION OF EFFECTIVE DOSE AND PRINCIPLES OF 
OPERATIONAL RADIATION PROTECTION 
Effective dose 
estimation. 
25. The Board shall, at any one time, be satisfied that the 
values and relationships to be used to estimate the relevant 
effective and equivalent doses as appropriate for external 
irradiation or for internal exposure from a radionuclide or mixture 
of radionuclides. 
Operational 
radiation 
protection of 
exposed workers. 
26. (1) Without prejudice to any other more detailed 
requirements in these regulation, it shall be the general duty of the 
radiation employer to develop, implement and document an 
appropriate system of operational radiation protection of exposed 
workers, including students, apprentices and other persons who 
might be affected by his practice or work activity, commensurate 
with the nature and extent of the risks associated with the practices 
or work activities and interventions under his responsibility and 
sufficient to ensure compliance with the requirements of these 
regulations, and, within this programme, to: 
(a) determine the measures and resources needed to 
achieve the protection and safety objectives and to 
ensure that the resources are provided and the 
measures properly implemented;

26 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(b) keep such measures and resources continually under 
review, and regularly to verify that the protection and 
safety objectives are being achieved; 
(c) identify any failures and shortcomings in the 
protection and safety measures and resources, and to 
take steps to correct them and prevent their recurrence; 
(d) establish arrangements, through representatives if 
appropriate, for facilitating consultation and 
cooperation between all relevant parties with respect 
to protection and safety; and 
(e) keep appropriate records regarding the discharge of 
their responsibilities. 
(2) This system of operational radiation protection referred to 
in subregulation (1) shall be based in particular on the following: 
(a) prior evaluation to identify the nature and magnitude 
of the radiological risk to exposed workers and 
implementation of the occupational dose limitation 
and optimization of radiation protection in all working 
conditions; 
(b) classification of workplaces into different areas, where 
appropriate, by reference to an assessment of the 
expected annual doses and the probability and 
magnitude of potential exposures; 
(c) classification of workers into different categories; 
(d) implementation of control measures and monitoring 
relating to the different areas and working conditions, 
including, where necessary, individual monitoring; 
(e) medical surveillance. 
(3) In the event of a breach of any applicable requirement of 
these regulations the radiation employer shall, as appropriate: 
(a) promptly inform the Board of any such breach, and 
whenever an emergency exposure situation has 
developed or is developing to also immediately inform 
the Civil Protection Department; 
(b) investigate the breach and its causes, circumstances 
and consequences; 
(c) take appropriate action to remedy the circumstances 
that led to the breach and to prevent a recurrence of 
similar breaches; 
(d) communicate to the Board, the causes of the breach 
and on the corrective or preventive actions taken or to 
be taken; as soon as possible and in any case by no 
later than ten working days; and 
(e) take any other actions that may be necessary as 
required by these regulations. 
(4) The Board may, if it considers it necessary, require a 
radiation employer to set up a specialised radiation protection unit, 
distinct from production operation units, to perform radiation

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 27 
protection tasks and provide specialist advice: 
Provided that such a unit may be shared by several 
installations. 
Risk assessment. 27. (1) Before a radiation employer commences a new 
practice or work activity involving work with ionising radiation in 
respect of which no risk assessment has been made by him, a 
suitable and sufficient assessment shall be made: 
(i) a review of design and operational aspects 
related to a source, which is relevant to the 
protection of persons or the safety of the source; 
(ii) analysis of the provisions for safety and 
protection established by the design and 
operation of the source. 
(2) The assessment referred to in subregulation (1) shall be: 
(a) in writing; 
(b) submitted to the Board as part of an application for 
notification or authorisation; 
(c) reviewed and amended as necessary and a copy of the 
latest assessment performed with any amendments 
made shall be kept at the practice. 
(3) Without prejudice to subregulation (1), a radiation 
employer shall not carry out work with ionising radiation unless he 
has made an assessment sufficient to demonstrate that: 
(a) analysis of risks associated with normal conditions and 
accidental situations; 
(b) the nature and magnitude of the risks to workers and 
other persons arising from those hazards have been 
evaluated. 
(4) Where the assessment made for the purposes of this 
regulation shows that a radiation risk to workers or other persons 
exists from an identifiable radiation accident, the radiation 
employer shall take all reasonably practicable steps to - 
(a) prevent any such accident; 
(b) limit the consequences of any such accident which 
does occur; and 
(c) provide workers with the appropriate information, 
instruction and training, and with the equipment 
necessary to restrict their exposure to ionising 
radiation. 
(5) The radiation employer shall also keep a record of the 
ongoing system of instruction and training that shall comply with 
minimum requirements to be set by the Board. 
PART VII 
CLASSIFICATION OF EXPOSED WORKERS, APPRENTICES, 
AND STUDENTS

28 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Categorization of 
exposed workers. 
28. (1) For the purposes of monitoring and surveillance, every 
radiation employer shall designate exposed workers in one of two 
categories: 
(a) category A: those exposed workers who are liable to 
receive an effective dose greater than 6 mSv per year 
or an equivalent dose greater than 3/10 of the dose 
limits for the lens of the eye, skin and extremities laid 
down in the Third Schedule; 
(b) category B: those exposed workers who are not 
classified as exposed category A workers. 
(2) The radiation employer shall immediately inform those 
workers that they have been so designated further to subregulation 
(1). 
(3) The radiation employer shall not designate a worker as a 
category A worker unless - 
(a) that worker is aged eighteen years or over; and 
(b) an approved medical practitioner or approved 
occupational health service has certified in the health 
record that that worker is fit for the work with ionising 
radiation which he is to carry out. 
(4) The radiation employer may cease to treat a radiation 
worker as a category A worker only at the end of a calendar year 
except where - 
(a) an approved medical practitioner or approved 
occupational health service so requires; or 
(b) the radiation worker is no longer employed by the 
same radiation employer in a capacity that is likely to 
result in significant exposure to ionising radiation 
during the remainder of the relevant calendar year. 
Information and 
training. 
29. Every radiation employer shall ensure that exposed 
workers, apprentices and students who, in the course of their work 
or studies are obliged to use sources, are given suitable and 
sufficient information, instruction and training on: 
(a) the health risks involved in their work including: 
(i) the general radiation protection procedures and 
precautions to be taken and, in particular, those 
involved with operational and working 
conditions in respect of both the practice or 
work activity in general and each type of work 
station or job to which they may be assigned, 
and 
(ii) the importance of complying with the technical, 
medical and administrative requirements;

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 29 
S.L. 424.11 
(b) in the case of women, the need for early declaration of 
pregnancy in view of the risks of exposure for the 
child to be born and the risk of contaminating the 
breastfeeding infant in case of bodily radioactive 
contamination and of the need to inform the employer 
as soon as possible as provided for in the Protection of 
Maternity at Work Places Regulations. 
Assessment and 
implementation of 
radiation 
protection 
measures. 
30. (1) The radiation employer shall be responsible for 
assessing and implementing arrangements for the radiological 
protection of exposed workers. 
(2) Subject to subregulation (4), every radiation employer shall 
consult such suitable qualified experts, as are necessary, for the 
purpose of advising the radiation employer as to the observance of 
these regulations and shall, in any event, consult one or more 
suitable qualified experts with regard to: 
(a) prior critical examination of plans for installations 
from the point of view of radiation protection; 
(b) the acceptance into service of new or modified sources 
from the point of view of radiation protection; 
(c) regular checking of the effectiveness of protective 
devices and techniques; 
(d) regular calibration of measuring instruments and 
regular checking that they are serviceable and 
correctly used; 
(e) periodical review (and update) of relevant procedures 
and documentation. 
(3) Where a qualified expert is consulted pursuant to the 
requirements of subregulation (2) (other than in respect of the 
observance of that subregulation), the radiation employer shall 
appoint that qualified expert in writing and shall include in that 
appointment the scope of the advice which the qualified expert is 
required to give. 
(4) Nothing in subregulation (2) shall require a radiation 
employer to consult a qualified expert where the only work with 
ionising radiation undertaken by that employer is work specified in 
regulation 18. 
(5) The radiation employer shall provide any qualified experts 
appointed by him with adequate information and facilities for the 
performance of his functions. 
PART VIII 
MEASURES FOR RESTRICTION OF EXPOSURE 
Restriction of 
exposure. 
31. (1) The radiation employer shall be responsible for 
assessing and implementing arrangements for the radiological 
protection of the public, workers and the environment. 
(2) Without prejudice to subregulation (1), every radiation 
employer shall, in relation to any work with ionising radiation that 
he undertakes, take all necessary steps to restrict so far as is 
reasonably practicable the extent to which his workers and the

30 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
public are exposed to ionising radiation. 
(3) Without prejudice to the generality of subregulation (2), a 
radiation employer shall so far as is reasonably practicable achieve 
the restriction of exposure to ionising radiation required under that 
subregulation by means of engineering controls and appropriate 
siting, design, features organisation and management system, 
operational procedures and in addition by the provision and use of 
safety features protective equipment and warning devices. 
(4) A radiation employer who provides personal protective 
equipment along with its relevant operating procedures, shall take 
all reasonable steps to ensure that the procedures are understood, 
adhered to and protective equipment is properly used or applied as 
the case may be. 
(5) Where it is appropriate to do so at the planning stage of 
radiation protection, dose constraints shall be used in restricting 
exposure to ionising radiation pursuant to subregulation (1). 
(6) Every radiation employer shall, for the purpose of 
determining whether the requirements of subregulation (1) are 
being met, ensure that an investigation is carried out forthwith 
when the effective dose under normal operation, received by any of 
his workers for the first time in any calendar year, exceeds 6mSv or 
such lower effective dose as the employer may specify in his 
radiation safety documentation. 
Maintenance and 
examination 
upgrade of control, 
monitoring 
equipment, 
operational 
procedures and 
personal protective 
equipment. 
32. (1) A radiation employer who provides any engineering 
control and monitoring equipment, design feature, operational 
procedures, personal protective equipment and safety feature or 
warning device to meet the requirements of regulation 31 shall 
ensure -
(a) that any such control, feature equipment or device is 
periodically and properly maintained and upgraded; 
and 
(b) where appropriate, that thorough examinations and 
tests of such controls, features equipment or devices 
are carried out at suitable intervals; and 
(c) a suitable record of that examination, maintenance and 
upgrade is made and kept for at least two years from 
the date on which the examination was made and that 
the record includes a statement of the condition of the 
equipment at the time of the examination. 
Personal protective 
equipment. 
S.L. 427.50 
33. Any personal protective equipment provided by an 
employer pursuant to regulation 32 shall comply with any provision 
in the Personal Protective Equipment Regulations, that is 
applicable to that item of personal protective equipment. 
Designation of 
controlled areas. 
34. (1) Every radiation employer shall designate as a 
controlled area any area under his control which has been identified 
by an assessment made by him (whether pursuant to regulation 27 
or otherwise) as an area in which - 
(a) it is necessary for any person who enters or works in 
the area to follow special procedures designed to

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 31 
restrict significant exposure to ionising radiation in 
that area or prevent or limit the probability and 
magnitude of radiation accidents or their effects; or 
(b) any person working in the area is likely to receive an 
effective dose greater than 6mSv a year or an 
equivalent dose greater than 3/10 of any relevant dose 
limit referred to in the Third Schedule in respect of a 
worker aged eighteen years or above. 
(2) An employer shall not intentionally create in any area 
conditions that would require that area to be designated as a 
controlled area unless that area is for the time being under the 
control of that employer. 
(3) The minimum requirements for a controlled area are as 
follows:
(a) the controlled area shall be delineated and access to it 
shall be restricted to individuals who have received 
appropriate instructions and shall be controlled in 
accordance with written procedures provided by the 
undertaking. Wherever there is a significant risk of the 
spread of radioactive contamination, specific 
arrangements shall be made, including for access and 
exit of individuals and goods; 
(b) taking into account the nature and extent of 
radiological risks in the controlled area, radiological 
surveillance of the working environment shall be 
organized in accordance with the provisions of 
regulations 37 and 38; 
(c) signs indicating type of area, nature of the sources and 
their inherent risks shall be displayed; 
(d) a warning symbol, recommended by ISO and signs 
indicating type of area, nature of the sources and their 
inherent risks shall be displayed; 
(e) working instructions appropriate to the radiological 
risk associated with the sources and the operations 
involved shall be laid down; 
(f) entrances and exists of controlled areas shall be 
provided with appropriate means for change of 
clothing, contamination monitoring and personal 
decontamination. 
(4) The implementation of these duties shall be carried out 
under the responsibility of the radiation employer following 
consultations with the approved occupational health service or the 
qualified experts, and the working conditions shall be kept under 
review. 
(5) Nothing in these regulations shall be construed as 
preventing a person from entering or remaining in a controlled area 
or a supervised area where that person enters or remains in any 
such area - 
(a) in the due exercise of a power of entry conferred on

32 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
him by or under any enactment; or 
(b) for the purpose of undergoing a medical exposure. 
(6) (a) The radiation employer of a controlled area in which 
outside workers perform activities shall be responsible, 
either directly or through contractual agreements, for 
the operational aspects of their radiological protection 
which are directly related to the nature of the 
controlled area and of the activities and shall ensure 
that the protection offered to the outside workers is 
equivalent to that given to his workers. 
(b) In particular, for each outside worker performing 
activities in a controlled area, the radiation employer 
must: 
(i) check that the radiation worker concerned has 
been passed as medically fit for the activities to 
be assigned to him; 
(ii) ensure that the radiation worker has received 
specific training in connection with the 
characteristics of both the controlled area and 
the activities; 
(iii) ensure that he has been issued with the necessary 
personal protective equipment; 
(iv) also ensure that he receives individual exposure 
monitoring appropriate to the nature of the 
activities, and any operational dosimetric 
monitoring that may be necessary; 
(v) ensure compliance with the general principles 
and limitation of doses referred to in regulation 
22; 
(vi) ensure that as soon as is reasonably practicable 
after the services carried out by that outside 
worker in that controlled area are completed, an 
estimate of the dose received by that radiation 
worker is entered into his radiation passbook; 
and 
(vii) when the radiation passbook of the outside 
worker is in the possession of that employer, the 
passbook is made available to that radiation 
worker upon request. 
(7) The external employer shall either directly or through 
contractual agreements with the radiation employer, ensure the 
operational radiological protection of their radiation workers as 
referred to in Part VI and this shall include appropriate measures to 
ensure: 
(a) limitation of doses 
(b) provision of information and training 
(c) individual exposure monitoring and records 
(d) medical surveillance.

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 33 
Designation of 
supervised areas 
35. (1) A radiation employer shall designate as a supervised 
area any area under his control, not being an area designated as a 
controlled area - 
(a) where it is necessary to keep the conditions of the area 
under review to determine whether the area should be 
designated as a controlled area; or 
(b) in which any person is likely to receive an effective 
dose greater than 1 mSv a year or an equivalent dose 
greater than 1/10 of any relevant dose limit referred to 
in the Third Schedule in respect of a worker aged 
eighteen years or above. 
(2) The requirements for a supervised area are as follows: 
(a) as a minimum, taking into account the nature and 
extent of radiological risks in the supervised area, 
radiological surveillance of the working environment 
shall be organized in accordance with the provisions of 
regulations 37 and 38; 
(b) the area shall be appropriately delineated and signs 
indicating type of area, nature of the sources and their 
inherent risks shall be displayed; 
(c) working instructions and operational procedures 
appropriate to the radiological risk associated with the 
sources and the operations involved shall be laid down 
and periodically reviewed to determine the possible 
need to revise the protection measures or safety 
provisions, including boundaries of the area. 
(3) The implementation of these duties shall be carried out 
under the responsibility of the radiation employer following 
consultations with the qualified experts or the approved 
occupational health service. 
Local rules and 
radiation 
protection 
supervisors. 
36. (1) For the purposes of enabling work with ionising 
radiation to be carried out in accordance with the requirements of 
these regulations, every radiation employer shall, in respect of any 
controlled area or, where appropriate having regard to the nature of 
the work carried out there, any supervised area, make and set down 
in writing such local rules as are appropriate to the radiation risk 
and the nature of the operations undertaken in that area. 
(2) The radiation employer shall take all reasonable steps to 
ensure that any local rules made pursuant to subregulation (1) are 
complied with. 
(3) The radiation employer shall ensure that such of those rules 
made pursuant to subregulation (1) as are relevant are brought to 
the attention of those workers and other persons who may be 
affected by them. 
(4) A radiation employer shall - 
(a) appoint one or more suitable radiation protection 
supervisors for the purpose of securing compliance 
with these regulations in respect of work carried out in 
any area made subject to local rules pursuant to

34 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
subregulation (1); and 
(b) set down in the local rules the names of such 
individuals so appointed. 
PART IX 
WORKPLACE MONITORING 
Monitoring of the 
workplace. 
37. (1) The radiation employer shall establish, maintain and 
keep under review a programme for sufficient radiological 
surveillance of controlled and supervised areas the workplace, 
commensurate with the nature and the risk associated with the 
source, which shall comprise, as appropriate: 
(a) the measurement of external dose rates, indicating the 
nature and quality of the radiation in question; 
(b) the measurement of air activity concentration and 
surface density of contaminating radioactive 
substances, indicating their nature and their physical 
and chemical states. 
(2) The results of these measurements shall be recorded and, if 
necessary, used for estimating individual doses, as provided for in 
regulation 38. 
Individual 
monitoring. 
38. (1) Every radiation employer shall ensure that individual 
monitoring to enable an assessment of all doses of ionising 
radiation received by exposed category A workers shall be 
systematically carried out and that records are kept of such 
assessments. 
(2) For the purposes of subregulation (1), the radiation 
employer shall make suitable arrangements with one or more 
approved dosimetry service for - 
(a) the making of systematic assessments of such doses by 
the use of suitable individual measurement for 
appropriate periods or, where individual measurement 
is inappropriate, by means of other suitable 
measurements; and 
(b) the making and maintenance of dose records relating 
to each category A worker. 
(3) The radiation employer shall provide the approved 
dosimetry service with such information concerning his workers as 
is necessary for the approved dosimetry service to comply with the 
arrangements made for the purposes of subregulation (2). 
(4) A radiation employer shall - 
(a) ensure that each outside worker employed by him is 
provided with a current individual radiation passbook 
which shall not be transferable to any other worker and 
in which shall be entered the particulars set out in the 
Fourth Schedule; and 
(b) make suitable arrangements to ensure that that 
employer keeps the particulars entered in the radiation 
passbook up-to-date during the continuance of the

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 35 
employment of the outside worker. 
(5) The radiation employer shall - 
(a) at the request of a category A worker employed by him 
(or of a person formerly employed by him as a 
category A worker) and on reasonable notice being 
given, obtain (where necessary from the approved 
dosimetry service) and make available to that person a 
copy of the dose record of that person; and 
(b) when a category A worker ceases to be employed by 
the employer, take all reasonable steps to provide to 
that person a copy of his termination record. 
(6) The radiation employer shall ensure that monitoring for 
category B workers shall be at least sufficient to demonstrate that 
such workers are correctly classified in category B: 
Provided that the Board may require the radiation employer 
to provide individual monitoring and if necessary individual 
measurements, using an approved dosimetric service, for category 
B workers. 
(7) The radiation employer shall keep separate records of any 
exposures, whether measured or estimated, pursuant to special 
authorisations and accidental or emergency situations. 
Estimated doses 
and special entries. 
39. (1) Where a dosemeter or other device is used to make any 
individual measurement under regulation 38(2) and that dosemeter 
or device is lost, damaged or destroyed or it is not practicable to 
assess the dose received by a Category A worker over any period, 
the radiation employer shall make an adequate investigation of the 
circumstances of the case with a view to estimating the dose 
received by that person during that period and either - 
(a) in a case where there is adequate information to 
estimate the dose received by that person, shall send to 
the approved dosimetry service an adequate summary 
of the information used to estimate that dose and shall 
arrange for the approved dosimetry service to enter the 
estimated dose in the dose record of that person; or 
(b) in a case where there is inadequate information to 
estimate the dose received by the Category A worker, 
shall arrange for the approved dosimetry service to 
enter a notional dose in the dose record of that person 
which shall be the proportion of the total annual dose 
limit for the relevant period; 
and in either case the radiation employer shall take reasonable steps 
to inform the Category A worker of that entry and arrange for the 
approved dosimetry service to identify the entry in the dose record 
as an estimated dose or a notional dose as the case may be. 
Dosimetry for 
accidents and 
emergency 
exposures. 
40. (1) Where any occurrence takes place, including 
accidental or emergency exposure, which is likely to result in a 
person receiving an effective dose of ionising radiation exceeding 
6mSv or an equivalent dose greater than three-tenths of any 
relevant dose limit, the radiation employer shall -

36 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(a) in the case of any worker to whom a dosemeter or 
other device has been issued in accordance with 
regulation 38(2), arrange for that dosemeter or device 
to be examined and for the dose received to be 
assessed by the approved dosimetry service as soon as 
possible; 
(b) in any other case, arrange for the dose to be assessed 
by an appropriate means as soon as possible, having 
regard to the advice of the qualified expert. 
(2) In such a case, the radiation employer shall - 
(a) take all reasonably practicable steps to inform each 
person for whom a dose assessment has been made of 
the result of that assessment; and 
(b) submit the results of individual monitoring to the 
Board without delay. 
Recording and 
reporting of 
results. 
41. (1) The radiation employer shall ensure that a dose record 
shall be retained during the working life involving exposure to 
ionizing radiation of exposed workers, and afterwards until the 
individual has or would have attained the age of seventy-five years, 
but in any case not less than thirty years from the termination of the 
work involving exposure and that this shall include: 
(a) a record of the exposures measured or estimated, as the 
case may be, of individual doses pursuant to 
regulations 23, 38, 39 and 40; 
(b) in the case of exposures referred to in regulations 39 
and 40, the reports relating to the circumstances and 
the action taken; 
(c) the results of workplace monitoring used to assess 
individual doses where necessary. 
(2) The exposure referred to in regulations 23, 39 and 40 shall 
b e r e c o r d e d s e p a r a t e l y i n t h e d o s e r e c o r d r e f e r r e d t o i n 
subregulation (1). 
(3) The results of the individual monitoring required by 
regulations 38, 39 and 40 shall be: 
(a) made available to the Board; 
(b) made available to the worker concerned in accordance 
with subregulation (5); 
(c) submitted to the qualified expert to interpret the 
efficiency of the employer’s radiation protection 
programme; 
(d) submitted to the approved medical practitioner or 
approved occupational health service in order to 
interpret their implications for human health, as 
provided for in regulation 43. 
(4) Each radiation employer shall ensure that workers have 
access at their request to the results of their individual monitoring, 
including the results of measurements which may have been used in 
estimating them, or of the assessments of their doses made as a

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 37 
result of workplace measurements. 
(5) The Board shall facilitate the appropriate exchange of all 
relevant information on the doses previously received by a worker 
in order to perform the medical examination prior to employment 
or classification as a category A worker pursuant to regulation 44 
and to control the further exposure of workers. 
PART X 
DUTIES OF PERSONS IN RELATION TO PRACTICES, WORK 
ACTIVITIES AND SOURCES 
Duties of persons 
in relation to 
practices, work 
activities and 
sources. 
42. (1) It shall be the duty of every person, whether a private 
individual or corporate body, to render all assistance and 
cooperation to any officer duly authorised to act on behalf of the 
Board in the lawful execution of any duty carried out to fulfil the 
Board’s functions and this shall include to permit access to 
premises and facilities in which radiation sources are located or 
expected to be located in order to obtain information about the 
status of radiation safety and verify compliance with regulatory 
requirements: 
Provided that such officers shall be provided with a 
document by the Executive Chairperson of the Board identifying 
them as being officers on official business of the Board and such a 
document shall be shown to the person whose assistance or 
cooperation is requested. 
(2) It shall be the duty of every person, whether a private 
individual or corporate body, to abide with any condition in any 
a u t h o r i s a t i o n i s s u e d b y t h e B o a r d , o r w i t h a n y o t h e r 
communication of the Board in respect to any safety measure 
required at a practice or work activity. 
(3) A person who is engaged in work with ionising radiation 
shall - 
(a) not knowingly expose himself or any other person to 
ionising radiation to an extent greater than is 
reasonably necessary for the purposes of his work; 
(b) exercise reasonable care while carrying out such work; 
(c) co-operate fully with the employer in the 
implementation of any measures taken at the 
workplace aimed at minimising exposure to ionising 
radiation; 
(d) take due consideration of any relevant information 
supplied to him and to participate fully in any 
instruction and training programmes considered 
necessary by the employer; 
(e) follow all applicable rules and procedures for a 
person’s protection and safety; and 
(f) immediately report any deficiency in measures 
referred to in paragraph (c) to the employer. 
(4) Every person who is engaged in work with ionising 
radiation and for whom personal protective equipment is provided

38 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
pursuant to regulation 31(3) shall - 
(a) make full and proper use of any such personal 
protective equipment; 
(b) forthwith report to his employer any defect he 
discovers in any such personal protective equipment; 
and 
(c) take all reasonable steps to ensure that any such 
personal protective equipment is returned after use to 
the accommodation provided for it. 
(5) It shall be the duty of every outside worker not to misuse 
the radiation passbook issued to him or falsify or attempt to falsify 
any of the information contained in it. 
(6) Any person to whom regulation 38(1) or regulation 55(4) 
relates shall comply with any reasonable requirement imposed on 
him by his employer for the purposes of making the measurements 
and assessments required under regulation 38(1) and regulation 
40(1). 
(7) A person who is subject to medical surveillance under 
regulation 43 shall, when required by his employer and at the cost 
of the employer, present himself during his working hours for such 
medical examination and tests as may be required for the purposes 
of subregulation (1) of that regulation and shall provide the 
approved medical practitioner or approved occupational health 
service with such information concerning his health as the 
approved medical practitioner or approved occupational health 
service may reasonably require. 
(8) A worker shall forthwith notify his employer if he has 
reasonable cause to believe that - 
(a) he or another person has received an overexposure; 
(b) an occurrence mentioned in regulation 64(1) or (2) has 
occurred. 
PART XI 
MEDICAL SURVEILLANCE OF EXPOSED WORKERS 
Medical 
surveillance. 
43. (1) The radiation employer shall ensure the appropriate 
medical surveillance of any exposed workers, and notwithstanding 
this overall responsibility, shall make use of the services of 
approved medical practitioners or approved occupational health 
services to carry out medical surveillance of Category A workers to 
ascertain their state of health as regards their fitness to perform 
work with ionising radiation. 
(2) Such surveillance shall apply to the following workers: 
(a) category A workers; 
(b) workers who have received an overexposure and are 
not category A workers; 
(c) workers who are engaged in work with ionising 
radiation subject to conditions imposed by an 
approved medical practitioner or approved

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 39 
occupational health service under subregulation (6). 
(3) Such surveillance shall include: 
(a) a thorough medical examination prior to employment 
or classification as a category A worker to determine 
the worker’s fitness for a post as a category A worker; 
(b) periodic reviews of health. 
(4) These examinations shall take into consideration the type of 
work and the individual worker’s state of health and shall be 
performed at a frequency of: 
(a) at least once a year, to ensure continued fitness to 
perform their duties, and 
(b) more than once a year if the approved medical 
practitioners considers it necessary. 
(5) The approved medical practitioners or approved 
occupational health service may indicate the need for medical 
surveillance to continue after cessation of work for as long as they 
consider it necessary to safeguard the health of the person 
concerned. 
(6) The radiation employer shall ensure that special medical 
surveillance shall be provided in each case where one of the dose 
limits laid down in the Third Schedule has been exceeded and shall 
ensure that any subsequent conditions of exposure shall be subject 
to the agreement of the approved medical practitioner or approved 
occupational health service. 
(7) The radiation employer shall further ensure that any 
measures considered necessary by the approved medical 
practitioner or approved occupational health service in relation to 
the health protection of the exposed individual such as further 
examinations, decontamination measures or urgent remedial 
treatment are carried out without undue delay. 
Medical 
classification. 
44. (1) After each examination to ascertain fitness for work as 
a category A worker, the approved medical practitioner or 
approved occupational health services shall classify the worker as: 
(a) fit, or 
(b) fit, subject to certain conditions, or 
(c) unfit. 
(2) Where the approved medical practitioner or approved 
occupational health service has certified in the health record of a 
Category A worker to whom this regulation relates that a worker 
should not be engaged in work with ionising radiation or that he 
should only be so engaged under conditions which have been 
specified in the health record, the employer shall not permit that the 
worker be engaged in the work with ionising radiation except in 
accordance with the conditions, if any, so specified. 
(3) Where, for the purpose of carrying out his functions under 
these regulations, an approved medical practitioner or approved 
occupational health service requires to inspect any workplace, the

40 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
employer shall permit him to do so. 
Health records. 45. The radiation employer shall ensure that a health record, 
containing the particulars referred to in the Fifth Schedule in 
respect of each worker referred to in regulation 43(2), shall be 
made and kept up to date for as long as he remains a worker of that 
category. Thereafter the record or a copy of it shall be retained until 
the individual has or would have attained the age of seventy-five 
years, but in any case not less than thirty years from the termination 
of the work involving exposure to ionizing radiation. 
Appeals. 46. Any person who feels aggrieved by a decision taken 
pursuant to regulation 43(6) and 44 may lodge an appeal with the 
Occupational Health and Safety Appeals Board and the decision 
taken by the Appeals Board shall be final. 
PART XII 
SIGNIFICANT INCREASE IN EXPOSURE DUE TO NATURAL 
RADIATION SOURCES 
Protection against 
exposure from 
terrestrial natural 
radiation sources. 
47. (1) It shall be the duty of the radiation employer to 
identify, by means of surveys or by any other appropriate means, 
work activities, not covered by regulation 4(1), within which the 
presence of natural radiation sources leads to a significant increase 
in the exposure of workers or of members of the public which 
cannot be disregarded from the radiation protection point of view. 
Such work activities include, in particular: 
(a) work activities where workers and, where appropriate, 
members of the public are exposed to thoron or radon 
daughters or gamma radiation or any other exposure in 
workplaces such as spas, caves, mines, underground 
workplaces and aboveground workplaces in identified 
areas; 
(b) work activities involving operations with, and storage 
of, materials, not usually regarded as radioactive but 
which contain naturally occurring radionuclides, 
causing a significant increase in the exposure of 
workers and, where appropriate, members of the 
public; 
(c) work activities which lead to the production of 
residues not usually regarded as radioactive but which 
contain naturally occurring radionuclides, causing a 
significant increase in the exposure of members of the 
public and, where appropriate, workers; 
(d) aircraft operation. 
(2) In situations where the radiation employer has identified 
work activities pursuant to subregulation (1), wherein exposure to 
natural radiation sources needed attention and had to be subject to 
control, the radiation employer shall be required to set up 
appropriate means for monitoring exposure and as necessary - 
(a) implement corrective measures to reduce exposure 
pursuant to all or part of Part XIV; 
(b) apply radiation protection measures pursuant to all or

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 41 
part of Parts IV, V, VI, VII, VIII, IX and XI. 
Protection of air 
crew. 
48. Every radiation employer operating aircraft shall take 
account of exposure to cosmic radiation of air crew who are liable 
to be subject to exposure to more than 1 mSv per year. The 
radiation employer shall take appropriate measures, in particular - 
(a) to assess the exposure of the crew concerned; 
(b) to take into account the assessed exposure when 
organizing working schedules with a view to reducing 
the doses of highly exposed aircrew; 
(c) to inform the workers concerned of the health risks 
their work involves; 
(d) to apply Part 3(2) and (3) of the Third Schedule to 
female air crew.
PART XIII 
IMPLEMENTATION OF RADIATION PROTECTION FOR THE 
POPULATION IN NORMAL CIRCUMSTANCES 
Basic principles. 49. It shall be the duty of the radiation employer to create the 
conditions necessary to ensure the best possible protection of other 
persons who may be affected by his practice or work activity, based 
on the principles set out in regulation 20 and to apply the 
fundamental principles governing operational protection of the 
population. 
Conditions for 
authorization of 
practices or work 
activities involving 
a risk from 
ionizing radiation 
from the 
population. 
50. (1) The radiation employer shall take all necessary 
measures to ensure, so far as reasonably practicable, the 
operational radiation protection of the population in normal 
circumstances from practices or work activities subject to prior 
authorization. 
(2) The radiation employer shall make all necessary 
arrangements and surveys for detecting and eliminating the factors 
which, in the course of any operation involving exposure to 
ionizing radiation, are liable to create a risk of exposure for the 
population which cannot be disregarded from the radiation 
protection point of view. 
(3) Radiation employers shall be responsible for implementing 
measures for: 
(a) ensuring the safety of sources, in order that the 
likelihood of public exposures is controlled in 
accordance with the requirements of these regulations; 
(b) suitable and adequate facilities, equipment and 
services for the protection of the public, the nature and 
extent of which are commensurate with the magnitude 
and likelihood of the exposure; 
(c) appropriate training in radiation safety and periodic retraining 
of the personnel having functions relevant to 
the protection of the public. 
Estimates of 
population doses. 
51. (1) Radiation employers shall, as appropriate, establish 
and carry out a monitoring programme, of magnitude and

42 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
complexity commensurate with the type of and risks associated 
with the sources under their responsibility, which is sufficient to 
ensure that the requirements of these regulations are satisfied and 
to assess the exposure of the members of the public from sources of 
external irradiation and, or discharges of radioactive substances 
into the environment. 
(2) The Board shall: 
(a) ensure that dose estimates from practices or work 
activities referred to in regulation 50 are made as 
realistic as possible for the population as a whole and 
for critical groups of the population in all places where 
such groups may occur; 
(b) decide on the frequency of assessments and take all 
necessary steps to identify the critical groups of the 
population, taking into account the effective pathways 
of transmission of the radioactive substances; 
(c) ensure, taking into account the radiological risks, that 
the estimates of the population doses include: 
(i) assessment of the doses due to external 
radiation, indicating, where appropriate, the 
quality of the radiation in question, 
(ii) assessment of the intake of radionuclides, 
indicating the nature of the radionuclides and, 
where necessary, their physical and chemical 
states, and determination of the activity and 
concentrations of these radionuclides, 
(iii) assessment of the doses that the critical groups 
of the population are liable to receive and 
specification of the characteristics of these 
groups: 
(d) require records to be kept relating to measurements of 
external exposure, estimates of intakes of 
radionuclides and radioactive contamination as well as 
the results of the assessment of the doses received by 
critical groups and by the population. 
Other duties of 
radiation 
employer. 
52. (1) Every radiation employer shall conduct his practice or 
work activity in accordance with the principles of health protection 
of the population in the area of radiation protection. 
(2) Without prejudice to the generality of subregulation (1), 
this shall, in particular, include the fulfilling of the following tasks: 
(a) achieving and maintaining an optimal level of 
protection of the environment and the population; 
(b) checking the effectiveness of technical devices for 
protecting the environment and the population; 
(c) acceptance into service application, from the point of 
view of surveillance monitoring of radiation 
protection, of equipment and procedures for measuring 
and assessing, as appropriate, exposures and 
radioactive contamination of the environment and the

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 43 
population; 
(d) correct use, regular maintenance and calibration of 
measuring instruments and regular checking that they 
are serviceable and correctly used aimed at obtaining 
true results; 
(e) maintaining and updating the records related to 
paragraphs (a) to (d). 
(3) The radiation employer shall make appropriate use of 
qualified experts and, if necessary, the specialized radiation 
protection unit referred to in regulation 26(4) to enable the 
appropriate discharge of these duties. 
Control of visitors. (4) The radiation employer shall - 
(a) ensure that visitors be accompanied in any controlled 
area by a person knowledgeable about the radiation 
safety measures for that area; 
(b) provide adequate information and instruction to 
visitors before they enter a controlled area so as to 
ensure appropriate protection of the visitors and of 
other individuals who may be affected by their actions; 
and 
(c) ensure that adequate control over entry of visitors to a 
supervised area be maintained and that appropriate 
signs be posted in such areas. 
PART XIV 
INTERVENTION 
Intervention in 
cases of 
radiological 
emergencies. 
53. (1) These requirements shall apply to intervention in cases 
of radiological emergencies or in cases of lasting exposure 
resulting from the after-effects of a radiological emergency or a 
past or old practice or work activity. 
(2) The implementation and extent of any intervention shall be 
considered in compliance with the following principles: 
(a) intervention shall be undertaken only if the reduction 
in detriment due to radiation is sufficient to justify the 
harm and costs, including social costs, of the 
intervention; 
(b) the form, scale and duration of the intervention shall 
be optimized so that the benefit of the reduction in 
health detriment less the detriment associated with the 
intervention, will be maximized; 
(c) dose limits, as laid down in the Third Schedule, shall 
not apply to intervention; however, the intervention 
levels established in application of regulation 58(1) 
constitute indications as to the situations in which 
intervention is appropriate; furthermore, in cases of 
long term exposure covered by regulation 59, the dose 
limits set out in Part 2 of the Third Schedule should 
normally be appropriate for workers involved in 
interventions.

44 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Potential 
exposures. 
54. The radiation employer shall, where appropriate, or if 
asked by the Board - 
(a) consider the possibility of radiological emergencies 
resulting from practices or work activities subject to 
the system of notification or authorization laid down in 
Part III; 
(b) make an assessment of the spatial and temporal 
distribution of the radioactive substances dispersed in 
the event of a possible radiological emergency; 
(c) make an assessment of the corresponding potential 
exposures. 
Requirements for a 
radiation 
employer’s 
emergency plan. 
55. (1) Where an assessment made in accordance with 
regulation 27 shows that a radiation accident is reasonably 
foreseeable (having regard to the steps taken by the radiation 
employer under subregulation (3) of that regulation), the radiation 
employer shall prepare an emergency plan designed to secure, so 
far as is reasonably practicable, the restriction of exposure to 
ionising radiation and the health and safety of persons who may be 
affected by such accident and to enable the assessment of 
corresponding potential exposures. 
(2) The radiation employer shall ensure that - 
(a) where local rules are required for the purposes of 
regulation 36, a copy of the emergency plan made in 
pursuance of subregulation (1), and approved by the 
Board, is identified in those rules and incorporated 
into them by way of summary or reference; 
(b) rehearsals of the arrangements in the plan are carried 
out at suitable intervals. 
(3) Emergency plans shall, as appropriate - 
(a) characterise extent of a potential emergency; 
(b) identify protective actions; 
(c) assign responsibilities for notifying the relevant 
authorities and for initiating and discharging 
protection and mitigation actions; 
(d) provide procedures and communication arrangements 
for contacting and obtaining assistance from the Civil 
Protection Department; 
(e) provide for training personnel involved in 
implementing emergency plans and for rehearsals at 
suitable intervals in conjunction with designated 
authorities; 
(f) provide for periodic review and update of the plan; 
(g) identify the public information arrangements in the 
event of an emergency; and 
(h) specify the criteria for terminating each protective 
action. 
(4) Any worker under his control who may be involved with or

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 45 
may be affected by arrangements in the plan has been given 
suitable and sufficient instructions and where appropriate issued 
with suitable dosemeters or other devices obtained in either case 
from the approved dosimetry service with which the radiation 
employer has entered into an arrangement under regulation 38. 
Intervention 
preparation. 
56. (1) The Civil Protection Department shall be responsible 
for preparing for and managing radiological emergencies which 
may occur in connection with practices or work activities on or 
outside Maltese territory and which may affect Malta. The response 
and management responsibilities of the Civil Protection 
Department shall not be limited to off-site emergencies but shall 
extend to any on-site emergencies which in the opinion of the Civil 
Protection Department, cannot be managed by the radiation 
employer. 
(2) Every radiation employer shall ensure that appropriate onsite 
intervention plans, taking account of the general principles of 
radiation protection for intervention referred to in regulation 53(2) 
and of the appropriate intervention levels established by the Board, 
are drawn up, in order to deal with various types of radiological 
emergency and that such plans are tested to an appropriate extent at 
regular intervals. 
(3) The Civil Protection Department shall make suitable 
provision for the appropriate training of personnel who may be 
involved in technical, medical and health intervention. 
(4) The Board shall be kept informed of: 
(a) the current situation and its expected evolution; 
(b) the measures taken to terminate the accident and to 
protect workers and members of the public; and 
(c) the exposures that have been incurred and that are 
expected to be incurred. 
Implementation of 
intervention. 
57. (1) The radiation employer shall immediately notify the 
Board and the Civil Protection Department, by the quickest 
practicable means, of any radiological emergency and shall take all 
appropriate action to reduce the consequences. 
(2) Without prejudice to the requirements in subregulation (1), 
the appropriate action shall include the carrying out of an initial 
provisional assessment of the circumstances and consequences of 
the emergency and rendering all the necessary assistance with 
intervention. 
(3) The radiation employer shall ensure that provision is made, 
if the situation so requires, for intervention related to: 
(a) the source, to reduce or stop the direct radiation and 
emission of radionuclides; 
(b) the environment, to reduce the spread of radioactve 
contamination; 
(c) individuals, to reduce exposure and organize the 
treatment of victims.

46 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(4) In the event of a radiological emergency on or outside 
Maltese territory, the Civil Protection Department shall be 
responsible for: 
(a) the organization of appropriate intervention, taking 
account of the real characteristics of the emergency; 
(b) the assessment and recording of the consequences of 
the radiological emergency and of the effectiveness of 
the intervention. 
(5) The Civil Protection Department shall, in the event of a 
radiological emergency occurring at an installation in Malta or 
being likely to have radiological consequences on Maltese 
territory, establish relations to obtain cooperation with any other 
State which may be involved. 
Emergency 
occupational 
exposure. 
58. (1) The Board shall establish exposure levels, taking into 
account the technical obligations and health risks, for situations 
where workers or intervention personnel involved in different kinds 
of intervention are liable to be subjected to emergency exposure 
resulting in doses in excess of the occupational dose limits for 
exposed workers. These levels are given in the Seventh Schedule 
and shall serve as operational guides. 
(2) It shall be the duty of the radiation employer to ensure 
adequate personal protective means, radiological monitoring and 
medical surveillance of any such workers or intervention personnel. 
Intervention in 
cases of long-term 
exposure. 
59. The Board shall ensure that when a situation leading to 
lasting exposure resulting from the after-effects of a radiological 
emergency or a past practice or work activity is identified, it shall, 
if necessary and to the extent of the exposure risk involved, ensure 
that: 
(a) the area concerned is demarcated; 
(b) arrangements for the monitoring of exposure are made; 
(c) any appropriate intervention is implemented, taking 
account of the real characteristics of the situation; 
(d) access to or use of land or buildings situated in the 
demarcated area is regulated. 
PART XV 
ARRANGEMENTS FOR THE CONTROL OF RADIOACTIVE 
SUBSTANCES, ARTICLES AND EQUIPMENT 
Sealed sources and 
articles containing 
or embodying 
radioactive 
substances. 
60. (1) Radiation employers shall ensure the safety of the 
sources under their responsibility, from the time of their acquisition 
throughout their entire operational life and up to their final 
disposal. 
(2) Where a radioactive substance is used, the radiation 
employer shall ensure that, whenever reasonably practicable, the 
substance is in a form of a sealed source. 
(3) The radiation employer shall ensure that the design, 
construction and maintenance of any article containing or 
embodying a radioactive substance, including its bonding,

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 47 
immediate container or other mechanical protection, is such as to 
prevent the leakage of any radioactive substance. 
(4) Where appropriate, the radiation employer shall ensure that 
suitable tests are carried out at suitable intervals to detect leakage 
of radioactive substances from any article under his control to 
which subregulation (3) applies and the employer shall make a 
suitable record of each such test and shall retain that record for at 
least two years after the article is disposed of or until a further 
record is made following a subsequent test to that article. 
Procurement and 
commissioning of 
sources. 
61. Radiation employers in co-operation with suppliers, shall - 
(a) ensure, on procurement of any new source or 
equipment containing radiation generator, that such 
sources or equipment conform to applicable 
international standards as may be approved by the 
Board; and 
(b) ensure that sources and equipment are tested to 
demonstrate compliance with the appropriate 
specifications. 
Accounting and 
security of 
radioactive 
substances. 
62. (1) Every radiation employer shall take such steps as are 
appropriate, for the purpose of controlling radioactive substances 
which are involved in work with ionising radiation which he 
undertakes: 
(a) to account for and keep up to date records of the 
quantity and location of radioactive substances by 
keeping written records of: 
(i) whenever the location of the source is changed, 
and 
(ii) annual verification of the employer’s source 
inventory; 
(b) to keep those records or a copy thereof for at least two 
years from the date on which they were made and, in 
addition, for at least two years from the date of 
disposal of that radioactive substance. 
(2) The records made pursuant to subregulation (1) shall be 
kept at the workplace and shall be readily available for inspection 
by the Board. 
Keeping and 
moving of 
radioactive 
substances. 
63. (1) Every radiation employer shall ensure, so far as is 
reasonably practicable, that any radioactive substance under his 
control which is not for the time being in use or being moved, 
transported or disposed of - 
(a) is kept in a suitable receptacle; and 
(b) is kept in a suitable store. 
(2) Every employer who causes or permits a radioactive 
substance to be moved (otherwise than by transporting it) shall 
ensure that, so far as is reasonably practicable, the substance is kept 
in a suitable receptacle, suitably labelled, while it is being moved. 
(3) Nothing in subregulations (1) or (2) shall apply in relation

48 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
to a radioactive substance while it is in or on the live body or 
corpse of a human being. 
Notification of 
certain 
occurrences. 
64. (1) Every radiation employer shall forthwith notify the 
Board in any case where a quantity of a radioactive substance 
which was under his control - 
(a) has been released or is likely to have been released 
into the atmosphere as a gas, aerosol or dust; or 
(b) has been spilled or otherwise released in such a 
manner as to give rise to significant radioactive 
contamination: 
Provided that such a release had not been exempted from 
regulatory control or had not been in a manner specified in an 
authorisation to dispose of radioactive waste issued by the Board. 
(2) Where a radiation employer has reasonable cause to believe 
that a quantity of a radioactive substance which was under his 
control is lost or has been stolen, the employer shall forthwith 
notify the Board of that loss or theft, as the case may be. 
(3) Where a radiation employer suspects or has been informed 
that an occurrence notifiable under subregulation (1) or (2) may 
have occurred, he shall make an immediate investigation and, 
unless that investigation shows that no such occurrence has 
occurred, he shall forthwith make a notification in accordance with 
the relevant subregulation. 
(4) A radiation employer who makes any investigation in 
accordance with subregulation (3) shall make a report of that 
investigation and shall, unless the investigation showed that no 
such occurrence occurred, keep that report or a copy thereof for at 
least fifty years from the date on which it was made or, in any other 
case, for at least two years from the date on which it was made. 
(5) The Board may issue guidance documents specifying the 
quantities of radioactive substances below which the provisions for 
notification referred to in subregulation (1) and (2) shall not apply. 
Misuse of or 
interference with 
sources of ionising 
radiation. 
65. No person shall intentionally or recklessly misuse or 
without reasonable excuse interfere with any radioactive substance 
or any electrical equipment to which these regulations apply. 
Appendices. 66. (1) The Board may from time to time publish Appendices 
to these regulations detailing specific requirements which have to 
be complied with by persons to which these requirements are 
addressed. 
(2) These appendices shall deal with, but are not limited to, the 
following: 
(a) occupational exposure; 
(b) medical exposure; 
(c) public exposure; 
(d) safety of sources; 
(e) emergency exposure situations

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 49 
(f) chronic exposure situations. 
PART XVI 
ENFORCEMENT 
Enforcement. 67. (1) Any breach of any of these regulations or of the 
Schedules or Appendices to these regulations shall be deemed an 
offence. 
(2) In any proceedings for an offence under these regulations 
consisting of a failure to comply with a duty or requirement to do 
something, it shall be for the accused to prove (as the case may be) 
that it was not practicable to do more than was in fact done to 
satisfy the requirement or duty, or that there was no better 
practicable means than was in fact used to satisfy the duty or 
requirement. 
(3) The enforcing regulatory authority for any breach of these 
regulations shall be as follows: 
(a) the Occupational Health and Safety Authority shall 
enforce the relevant statutory provisions in Parts IV to 
XII, excluding regulation 19(4), and Part XV; 
(b) the Superintendent of Public Health shall enforce the 
relevant statutory provisions in Part XIII; 
(c) the Environment Protection Directorate shall enforce 
the relevant statutory provisions in regulation 19(4); 
Cap. 411. 
(d) the Civil Protection Department shall enforce any 
breach of regulations relating to intervention in Part 
XIV as a breach of the Civil Protection Act: 
Cap. 365. 
Provided that any person found guilty of an offence in 
terms of Part II shall be considered to have breached the provisions 
of the National Interest (Enabling Powers) Act and be liable to a 
fine not exceeding fifty thousand liri.

50 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
FIRST SCHEDULE 
Regulation 17 
PARTICULARS TO BE PROVIDED IN A NOTIFICATION UNDER 
REGULATION 17 
The following particulars shall be given in a notification under regulation 17: 
(a) the name and address of the employer and a contact telephone or fax 
number or electronic mail address; 
(b) the address of the premises where or from where the work activity is to 
be carried out and a telephone or fax number or electronic mail address 
at such premises; 
(c) the nature of the business of the employer; 
(d) characteristics of the source, as a minimum - the source term, total 
activity, date and place of manufacturing and physical and chemical 
form of the radioactive substance; 
(e) into which of the following categories the source or sources of ionising 
radiation fall- 
(i) sealed source; 
(ii) unsealed radioactive substance; 
(iii) electrical equipment; 
(f) whether or not any source is to be used at premises other than the 
address given at sub-paragraph (b) above; 
(g) dates of notitication and commencement of the work activity; and 
(h) a written risk assessment pursuant to regulation 27. 
SECOND SCHEDULE 
Regulation 18 
QUANTITIES AND CONCENTRATIONS OF RADIONUCLIDES 
CRITERIA TO BE CONSIDERED FOR THE APPLICATION 
OF REGULATION 18 
1. A practice or work activity may be exempted from the requirement to report 
without further consideration, in compliance with regulation 18(1)(a) or (b) 
respectively, if either the quantity or the activity concentration, as appropriate, of the 
relevant radionuclides does not exceed the values in column 2 or 3 of Table A. 
2. The basic criteria for the calculation of the values in Table A, for the 
application of exemptions for practices or work activities, are as follows: 
(a) the radiological risks to individuals caused by the exempted practice or 
work activity are sufficiently low as to be of no regulatory concern; and 
(b) the collective radiological impact of the exempted practice or work 
activity is sufficiently low as to be of no regulatory concern under the 
prevailing circumstances; and 
(c) the exempted practice or work activity is inherently without

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 51 
radiological significance, with no appreciable likelihood of scenarios 
that could lead to a failure to meet the criteria in (a) and (b). 
3. Exceptionally, as provided in regulation 18(1)(a) and (b), the Board may 
decide that a practice or work activity may be exempted where appropriate without 
further consideration, in accordance wuth the basic criteria, even if the relevant 
radionuclides deviate from the values in Table A, provided that the following criteria 
are met in all feasible circumstances: 
(a) the effective dose expected to be incurred by any member of the public 
due to the exempted practice or work activity is of the order of 10 µSv 
or less in a year; and 
(b) either the collective effective dose committed during one year of 
performance of the practice or work activity is no more than about 1 
man . Sv or an assessment of the optimization of protection shows that 
exemption is the optimum option; 
(c) number of exempted practices or work activities at the same site and 
affecting the same critical group(s) shall be determined by the Board on 
case by case basis. 
4. For radionuclides not listed in Table A, the Board shall assign appropriate 
values for the total activities and concentrations of activity per unit mass where the 
need arises. Values thus assigned shall be complementary to those in Table A. 
5. The values laid down in Table A apply to the total inventory of radioactive 
substances held by a person or undertakings as part of a specific practice or work 
aclivity at any point in time and to a limited amount of radioactive material, not 
exceeding 1 tonne.(1000kg). 
6. Nuclides carrying the suffix "+" or "sec" in Table A represent parent 
nuclides in equilibrium with their correspondent daughter nuclides as listed in Table 
B. In this case the values driven in Table A refer to the parent nuclide alone, but 
already take account of the daughter nuclide(s) present. 
7. In all other cases of mixtures of more than one nuclide, the requiretnent for 
notification may be waived if the sum of the ratios for each nuclide of the total 
activity present divided by the value listed in Tahle A is less than or equal to l. This 
summation rule also applies to activity concentrations where the various nuclides 
concerned are contained in the same matrix. 
Table A 
Table of Radionuclides 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g) 
Hydrogen 
Tritiated compounds 1 106 1 109 
Beryllium 
Be-7 1 103 1 107 
Carbon 
C-14 1 104 1 107 
Fluorine 
F-18 1 101 1 106

52 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Neon 
Ne-19 1 102 1 109 
Sodium 
Na-22 1 101 1 106 
Na-24 1 101 1 105 
Silicon 
Si-31 1 103 1 106 
Si-32 1 103 1 106 
Phosphorus 
P-32 1 103 1 105 
P-33 1 105 1 108 
Sulphur 
S-35 1 105 1 108 
Chlorine 
Cl-36 1 104 1 106 
Cl-38 1 101 1 105 
Argon 
Ar-37 1 106 1 108 
Ar-41 1 102 1 109 
Potassium 
K-40 1 102 1 106 
K-42 1 102 1 106 
K-43 1 101 1 106 
K-44 1 101 1 105 
Calcium 
Ca-45 1 104 1 107 
Ca-47 1 101 1 106 
Scandium 
Sc-46 1 101 1 106 
Sc-47 1 102 1 106 
Sc-48 1 101 1 105 
Vanadium 
V-48 1 101 1 105 
Chromium 
Cr-51 1 103 1 107 
Manganese 
Mn-51 1 101 1 105 
Mn-52 1 101 1 105 
Mn-52m 1 101 1 105 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 53 
Mn-53 1 104 1 109 
Mn-54 1 101 1 106 
Mn-56 1 101 1 105 
Iron 
Fe-52 1 101 1 106 
Fe-55 1 104 1 106 
Fe-59 1 101 1 106 
Cobalt 
Co-55 1 101 1 106 
Co-56 1 101 1 105 
Co-57 1 102 1 106 
Co-58 1 101 1 106 
Co-58m 1 104 1 107 
Co-60 1 101 1 105 
Co-60m 1 103 1 106 
Co-61 1 102 1 106 
Co-62m 1 101 1 105 
Nickel 
Ni-59 1 104 1 108 
Ni-63 1 105 1 108 
Ni-65 1 101 1 106 
Copper 
Cu-64 1 102 1 106 
Zinc 
Zn-65 1 101 1 106 
Zn-69 1 104 1 106 
Zn-69m 1 102 1 106 
Gallium 
Ga-72 1 101 1 105 
Germanium 
Ge-71 1 104 1 108 
Arsenic 
As-73 1 103 1 107 
As-74 1 101 1 106 
As-76 1 102 1 105 
As-77 1 103 1 106 
Selenium 
Se-75 1 102 1 106 
Bromine 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

54 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Br-82 1 101 1 106 
Krypton 
Kr-74 1 102 1 109 
Kr-76 1 102 1 109 
Kr-77 1 102 1 109 
Kr-79 1 103 1 105 
Kr-81 1 104 1 107 
Kr-83m 1 105 1 1012 
Kr-85 1 105 1 104 
Kr-85m 1 103 1 1010 
Kr-87 1 102 1 109 
Kr-88 1 102 1 109 
Rubidium 
Rb-86 1 102 1 105 
Strontium 
Sr-85 1 102 1 106 
Sr-85m 1 102 1 107 
Sr-87m 1 102 1 106 
Sr-89 1 103 1 106 
Sr-90+ 1 102 1 104 
Sr-91 1 101 1 105 
Sr-92 1 101 1 106 
Yttrium 
Y-90 1 103 1 105 
Y-90m 1 101 1 106 
Y-91 1 103 1 106 
Y-91m 1 102 1 106 
Y-92 1 102 1 105 
Y-93 1 102 1 105 
Zirconium 
Zr-93+ 1 103 1 107 
Zr-95 1 101 1 106 
Zr-97+ 1 101 1 105 
Niobium 
Nb-93m 1 104 1 107 
Nb-94 1 101 1 106 
Nb-95 1 101 1 106 
Nb-95m 1 102 1 107 
Nb-97 1 101 1 106 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 55 
Nb-98 1 101 1 105 
Molybdenum 
Mo-90 1 101 1 106 
Mo-93 1 103 1 108 
Mo-99 1 102 1 106 
Mo-101 1 101 1 106 
Technetium 
Tc-96 1 101 1 106 
Tc-96m 1 103 1 107 
Tc-97 1 103 1 108 
Tc-97m 1 103 1 107 
Tc-99 1 104 1 107 
Tc-99m 1 102 1 107 
Ruthenium 
Ru-97 1 102 1 107 
Ru-103 1 102 1 106 
Ru-105 1 101 1 106 
Ru-106+ 1 102 1 105 
Rhodium 
Rh-103m 1 104 1 108 
Rh-105 1 102 1 107 
Palladium 
Pd-103 1 103 1 108 
Pd-109 1 103 1 106 
Silver 
Ag-105 1 102 1 106 
Ag-108m+ 1 101 1 106 
Ag-110m 1 101 1 106 
Ag-111 1 103 1 106 
Cadmium 
Cd-109 1 104 1 106 
Cd-115 1 102 1 106 
Cd-115m 1 103 1 106 
Cd-117 1 101 1 106 
Indium 
In-111 1 102 1 106 
In-113m 1 102 1 106 
In-114m 1 102 1 106 
In-115m 1 102 1 106 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

56 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Tin 
Sn-113 1 103 1 107 
Sn-125 1 102 1 105 
Antimony 
Sb-122 1 102 1 104 
Sb-124 1 101 1 106 
Sb-125 1 102 1 106 
Tellurium 
Te-123 1 103 1 106 
Te-125m 1 103 1 107 
Te-127 1 103 1 106 
Te-127m 1 103 1 107 
Te-129 1 102 1 106 
Te-129m 1 103 1 106 
Te-131 1 102 1 105 
Te-131m 1 101 1 106 
Te-132 1 102 1 107 
Te-133 1 101 1 105 
Te-133m 1 101 1 105 
Te-134 1 101 1 106 
Iodine 
I-123 1 102 1 107 
I-125 1 103 1 106 
I-126 1 102 1 106 
I-129 1 102 1 105 
I-130 1 101 1 106 
I-131 1 102 1 106 
I-132 1 101 1 105 
I-133 1 101 1 106 
I-134 1 101 1 105 
I-135 1 101 1 106 
Xenon 
Xe-131m 1 104 1 104 
Xe-133 1 103 1 104 
Xe-135 1 103 1 1010 
Caesium 
Cs-129 1 102 1 105 
Cs-131 1 103 1 106 
Cs-132 1 101 1 105 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 57 
Cs-134 1 101 1 104 
Cs-134m 1 103 1 105 
Cs-135 1 104 1 107 
Cs-136 1 101 1 105 
Cs-137+ 1 101 1 104 
Cs-138 1 101 1 104 
Barium 
Ba-131 1 102 1 106 
Ba-140+ 1 101 1 105 
Lanthanum 
La-140 1 101 1 105 
Cerium 
Ce-139 1 102 1 106 
Ce-141 1 102 1 107 
Ce-143 1 102 1 106 
Ce-144+ 1 102 1 105 
Praseodymium 
Pr-142 1 102 1 105 
Pr-143 1 104 1 106 
Neodymium 
Nd-147 1 102 1 106 
Nd-149 1 102 1 106 
Promethium 
Pm-147 1 104 1 107 
Pm-149 1 103 1 106 
Samarium 
Sm-151 1 104 1 108 
Sm-153 1 102 1 106 
Europium 
Eu-152 1 101 1 106 
Eu-152m 1 102 1 106 
Eu-154 1 101 1 106 
Eu-155 1 102 1 107 
Gadolinium 
Gd-153 1 102 1 107 
Gd-159 1 103 1 106 
Terbium 
Tb-160 1 101 1 106 
Dysprosium
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

58 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Dy-165 1 103 1 106 
Dy-166 1 103 1 106 
Holmium 
Ho-166 1 103 1 105 
Erbium 
Er-169 1 104 1 107 
Thulium 
Tm-170 1 103 1 106 
Tm-171 1 104 1 108 
Ytterbium 
Yb-175 1 103 1 107 
Lutetium 
Lu-177 1 103 1 107 
Hafnium 
Hf-181 1 101 1 106 
Tantalum 
Ta-182 1 101 1 104 
Tungsten 
W-181 1 103 1 107 
W-185 1 104 1 107 
W-187 1 102 1 106 
Rhenium 
Re-186 1 103 1 106 
Re-188 1 102 1 105 
Osmium 
Os-185 1 101 1 106 
Os-191 1 102 1 107 
Os-191m 1 103 1 107 
Os-193 1 102 1 106 
Iridium 
Ir-190 1 101 1 106 
Ir-192 1 101 1 104 
Ir-194 1 102 1 105 
Platinum 
Pt-191 1 102 1 106 
Pt-193m 1 103 1 107 
Pt-197 1 103 1 106 
Pt-197m 1 102 1 106 
Gold 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 59 
Au-198 1 102 1 106 
Au-199 1 102 1 106 
Mercury 
Hg-197 1 102 1 107 
Hg-197m 1 102 1 106 
Hg-203 1 102 1 105 
Thallium 
Tl-200 1 101 1 106 
Tl-201 1 102 1 106 
Tl-202 1 102 1 106 
Tl-204 1 104 1 104 
Lead 
Pb-203 1 102 1 106 
Pb-210+ 1 101 1 104 
Pb-212+ 1 101 1 105 
Bismuth 
Bi-206 1 101 1 105 
Bi-207 1 101 1 106 
Bi-210 1 103 1 106 
Bi-212+ 1 101 1 105 
Polonium 
Po-203 1 101 1 106 
Po-205 1 101 1 106 
Po-207 1 101 1 106 
Po-210 1 101 1 104 
Astatine 
At-211 1 103 1 107 
Radon 
Rn-220+ 1 104 1 107 
Rn-222+ 1 101 1 108 
Radium 
Ra-223+ 1 102 1 105 
Ra-224+ 1 101 1 105 
Ra-225 1 102 1 105 
Ra-226+ 1 101 1 104 
Ra-227 1 102 1 106 
Ra-228+ 1 101 1 105 
Actinium 
Ac-228 1 101 1 106 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

60 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Thorium 
Th-226+ 1 103 1 107 
Th-227 1 101 1 104 
Th-228+ 1 100 1 104 
Th-229+ 1 100 1 103 
Th-230 1 100 1 104 
Th-231 1 103 1 107 
Th-232 1 101 1 104 
Th-232sec 1 100 1 103 
Th-234+ 1 103 1 105 
Protactinium 
Pa-230 1 101 1 106 
Pa-231 1 100 1 103 
Pa-233 1 102 1 107 
Uranium 
U-230+ 1 101 1 105 
U-231 1 102 1 107 
U-232+ 1 100 1 103 
U-233 1 101 1 104 
U-234 1 101 1 104 
U-235 1 101 1 104 
U-236 1 101 1 104 
U-237 1 102 1 106 
U-238+ 1 101 1 104 
U-238sec 1 100 1 103 
U-239 1 102 1 106 
U-240 1 103 1 107 
U-240+ 1 101 1 106 
Neptunium 
Np-237+ 1 100 1 103 
Np-239 1 102 1 107 
Np-240 1 101 1 106 
Plutonium 
Pu-234 1 102 1 107 
Pu-235 1 102 1 107 
Pu-236 1 101 1 104 
Pu-237 1 103 1 107 
Pu-238 1 100 1 104 
Pu-239 1 100 1 104 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 61 
Note 1. In the case of radionuclides not specified elsewhere in this Part, the 
Pu-240 1 100 1 103 
Pu-241 1 102 1 105 
Pu-242 1 100 1 104 
Pu-243 1 103 1 107 
Pu-244 1 100 1 104 
Americium 
Am-241 1 100 1 104 
Am-242 1 103 1 106 
Am-242m+ 1 100 1 104 
Am-243+ 1 100 1 103 
Curium 
Cm-242 1 102 1 105 
Cm-243 1 100 1 104 
Cm-244 1 101 1 104 
Cm-245 1 100 1 103 
Cm-246 1 100 1 103 
Cm-247 1 100 1 104 
Cm-248 1 100 1 103 
Berkelium 
Bk-249 1 103 1 106 
Californium 
Cf-246 1 103 1 106 
Cf-248 1 101 1 104 
Cf-249 1 100 1 103 
Cf-250 1 101 1 104 
Cf-251 1 100 1 103 
Cf-252 1 101 1 104 
Cf-253 1 102 1 105 
Cf-254 1 100 1 103 
Einsteinium 
Es-253 1 102 1 105 
Es-254 1 101 1 104 
Es-254m 1 102 1 106 
Fermium 
Fm-254 1 104 1 107 
Fm-255 1 103 1 106 
Other radionuclides not 
listed above (see note 1) 
1 10-1 1 103 
1 2 3 
Radionuclide name, symbol, 
isotope 
Concentration for 
notification. 
Regulation 18 (Bq/g) 
Quantity for notification. 
Regulation 18 (Bq/g)

62 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
quantities specified in this entry are to be used unless the Board has approved some 
other quantity for that radionuclide. 
Note 2. Nuclides carrying the suffix "+" or "sec" in the above table represent 
parent nuclides in equilibrium with their correspondent daughter nuclides as listed in 
the following Table. In this case the concentrations and quantities given in the above 
Table refer to the parent nuclide alone, but already take account of the daughter 
nuclide(s) present. 
Table B 
List of nuclides in secular equilibrium as referred to in point 6 of this Schedule 
Parent nuclide Daughter nuclides 
Sr-80+ Rb-82 
Sr 90+ Y-90 
Zr-93+ Nb-93m 
Zr-97+ Nb-97 
Ru-106+ Rh-106 
Cs-137+ Ba-137m 
Ba-140+ La-140 
Ce-134+ La-134 
Ce-144+ Pr-144 
Pb-210+ Bi-210, Po-210 
Bi-210m+ Tl-206 
Pb-212+ Bi-212, Tl-208, Po-212 
Bi-212+ Tl-208, Po-212 
Rn-220+ Po-216 
Rn-222+ Po-218, Pb-214, Bi-214, Po-214 
Ra-223+ Rn-219, Po-215, Pb-211, Bi-211, Tl-207 
Ra-224+ Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 
Ra-226+ Rn-222, Po-218, Pb-214, Bl-214, Po-214, Pb-210, Bi-210, 
Po-210 
Ra-228+ Ac-228 
Th-226+ Ra-222, Rn-218, Po-214 
Th-228+ Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 
Th-229+ Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 
Th-232sec Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, 
Bi-212, Tl-208, Po-212 
Th-234+ Pa-234m 
U-230+ Th-226, Ra-222, Rn-218, Po-214 
U-232+ Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, 
Po-212 
U-235+ Th-231 
U-238+ Th-234, Pa-234m 
U-238sec Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, 
Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 
U-240+ Np-240

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 63 
THIRD SCHEDULE 
Regulation 22 
DOSE LIMITS FOR DIFFERENT CLASSES OF PERSONS 
Dose limit applies to the sum of the relevant doses from external exposures in one 
year and the committed doses from intakes in the same period. 
PART 1 
Dose limits for apprentices and students 
(1) The limit for effective dose for apprentices or students aged between 16 and 
18 years who, in the course of their studies, are obliged to use sources shall be 6 mSv 
per year.
Without prejudice to this dose limit: 
(a) the limit on equivalent dose for the lens of the eye shall be 50 mSv in a 
year; 
(b) the limit on equivalent dose for the skin shall be 150 mSv in a year. This 
limit shall apply to the dose averaged over any area of 1 cm2, regardless 
of the area exposed; 
(c) the limit on equivalent dose for the hands, forearms, feet and ankles 
shall be 150 mSv in a year. 
(2) The exposure conditions and operational protection of apprentices and 
students aged between 16 and 18 years referred to in paragraph (1) shall be 
equivalent to that of exposed workers of category B. 
(3) The dose limits for apprentices and students aged 18 years or over who, in 
the course of their studies, are obliged to use sources shall be as the dose limits for 
exposed workers laid down in Part 2. 
(4) The dose limits for apprentices and students who are not subject to the 
provisions of paragraph (1) and (3) shall be the same as the dose limits for members 
of the public specified in Part 4. 
PART 2 
Dose limits for exposed workers 
(1) For the purposes of regulation 22(1), the limit on effective dose for any 
worker of 18 years of age or above shall be 20 mSv in any calendar year. 
(2) Where an employer is able to demonstrate in respect of any worker that this 
dose limit is impracticable having regard to the nature of the work undertaken by 
that worker, the limit on effective dose for such exposed workers shall be 100 mSv 
in a consecutive five-year period, subject to a maximum effective dose of 50 mSv in 
any calendar year. 
Np-237+ Pa-233 
Am-242m+ Am-242 
Am-243+ Np-239 
Parent nuclide Daughter nuclides

64 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(3) Without prejudice to paragraphs (1) and (2): 
(a) the limit on equivalent dose for the lens of the eye shall be 150 mSv in a 
year; 
(b) the limit on equivalent dose for the skin shall be 500 mSv in a year. This 
limit shall apply to the dose averaged over any area of 1 cm2, regardless 
of the area eaposed; 
(c) the limit on equivalent dose for the hands, forearms, feet and ankles 
shall be 500 mSv in a year. 
PART 3 
Women of reproductve capacity 
(1) Without prejudice to the above paragraphs, the limit on equivalent dose for 
the abdomen of a woman of reproductive capacity who is at work, being the 
equivalent dose from extrnal radiation resulting from exposure to ionising radiation 
averaged throughout the abdomen, shall be 13 mSv in any consecutive period of 
three months. 
(2) As soon as a pregnat woman informs the undertaking, in accordance with the 
Protcction of Maternity at Workplaces Regulations, of her condition, the protection 
of the child to be born shall be comparable wuth that provded for members of the 
public. The conditions for the pregnant woman in the context of her employment 
shall therefore be such that the equivalent dose to the child to be born will be as low 
as reasonably achievable and that it will be unlikely that this dose will exceed 1 mSv 
during at least the remainder of the pregnancy. 
(3) As soon as a breastfeeding woman informs the undertaking in accordance 
with the Protection of Maternity at Workplaces Regulations of her condition she 
shall be employed so that 1/20 of the annual limit intake (ALI) shall not be 
exceeded. 
PART 4 
Other persons 
(1) Subject to paragraph (2) hereof, for the purposes of regulation 22(1) the 
limit on effective dose for any person other than a worker or trainee, including any 
person below the age of 16, attributable to practices or work activities, shall be 1 
mSv in any calendar year. 
(2) Paragraph (1) shall not apply in relation to any person (not being a 
comforter or carer) who may be exposed to ionising radiation resulting from the 
medical exposure of another person and in such a case the limit on effective dose for 
any such person shall be 5 mSv in any period of five consecutive calendar years. 
(3) Without prejudice to paragraphs (1) and (2) - 
(a) the limit on equivalent dose for the lens of the eye shall be 15 mSv in 
any calendar year; 
(b) the limit on equivalent dose for the skin shall be 50 mSv in any calendar 
year averaged over any 1 cm2 area regardless of the area exposed; 
(c) the limit on equivalent dose for the hands, forearms, feet and ankles 
shall be 50 mSv in a calendar year: 
Provided that the dose limits from all relevant practices or work activities 
shall not apply to any of the following exposures: 
(a) exposure of individuals as part of their own medical diagnosis or

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 65 
treatment; 
(b) exposure of individuals knowingly and willingly helping (other than as 
part of their occupation) in the support and comfort of patients 
undergoing medical diagnosis or treatment. The dose of any such 
comforter or visitor of patients shall be constrained so that it is unlikely 
that his dose will exceed 5 mSv during the period of patient’s 
examination or treatment. The dose to children visiting patients, who 
have ingested radioactive materials, should similarly be constrained to 
less than 1 mSv; 
(c) exposure of volunteers participating in medical and biomedical research 
programmes. 
(4) Generic dose constraints: 
In relation to regulation 21, the generic dose constraint of effective dose, 
applicable to a single practice or work activity and to the mean dose among 
individuals of the critical group of the public, shall be 0.25 mSv/y. 
FOURTH SCHEDULE 
Rcgulation 38(4) 
PARTICULARS TO BE ENTERED IN THE RADIATION PASSBOOK 
1. Indivdual serial number of the passbook. 
2. A statement that the passbook has been approved by the Board for the 
purpose of these Regulations. 
3. Datc of issue of the passbook by the approved dosimetry service. 
4. The name, telephone number and mark of endorsement of the issuing 
approved dosimetry service. 
5. The name, address, telephone and telex/fax number of the employer. 
6. Full name (surname, forenames), date of birth, gender and identity card 
number and/or national insurance number of the outside worker to whom the 
passbook has been issued. 
7. Date of the last medical review of the outside worker and the relevant 
classification in the health record maintained under regulation 44 as fit, fit subject to 
conditions (which shall be specified) or unfit. 
8. The relevant dose limits applicable to the outside worker to whom the 
passbook has been issued. 
9. The cumulative dose assessment in mSv for the year to date for the outside 
worker, external (whole body, organ or tissue) and/or internal as appropriate and the 
date of the end of the last assessment period. 
10. In respect of services performed by the outside worker - 
(a) the name and address of the employer responsible for the controlled 
area; 
(b) the period covered by the performance of the services; 
(c) estimated dose information, which shall be, as appropriate -

66 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
(i) all estimate of any whole body effective dose in mSv received by 
the outside worker; 
(ii) in the event of non-uniform esposure, an estimate of the 
equivalent dose in mSv to organs and tissues as appropriate; and 
(iii) in the event of internal radioactive contamination, an estimate of 
the activity taken in or the committed dose. 
FIFTH SCHEDULE 
Regulation 45 
PARTICULARS TO BE CONTAINED IN A HEALTH RECORD 
The following particulars shall be contained in a health record made for the 
purposes of regulation 45 - 
(a) the worker’s - 
(i) full name; 
(ii) sex; 
(iii) date of birth; 
(iv) permanent address; and 
(v) Identity Card number and/or National Insurance number; 
(b) the date of the worker’s commencement as a classified person in present 
employment; 
(c) the nature of the worker’s employment; 
(d) in the case of a female worker, a statement as to whether she is likely to 
receive in any consecutive period of three months an equivalent dose of 
ionising radiation for the abdomen exceeding 13 mSv; 
(e) the date of last medical examination or health review carried out in 
respect of the worker; 
(f) the type of the last medical examination or health review carried out in 
respect of the worker; 
(g) a statement by the approved medical practitioner or approved 
occupational health service made as a result of the last medical 
examination or health review carried out in respect of the worker 
classifying the worker as fit, fit subject to conditions (which should be 
specified) or unfit; 
(h) in the case of a female worker in respect of whom a statement has been 
made under paragraph (d) to the effect that she is likely to receive in 
any consecutive period of three months an equivalent dose of ionising 
radiation for the abdomen exceeding 13 mSv, a statement by the 
approved medical practitioner or approved occupational health service 
certifying whether in his professional opinion the worker should be 
subject to the additional dose limit specified in paragraph (1) of Part 3 
of the Third Schedule; 
(i) in relation to each medical examination and health review, the name and 
signature of the approved medical practitioner or approved occupational 
health service;

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 67 
(j) the name and address of the approved dosimetry service with whom 
arrangements have been made for maintaining the dose record in 
accordance with regulation 38. 
SIXTH SCHEDULE 
Regulation 5 
CONVENTION ON PHYSICAL PROTECTION OF NUCLEAR MATERIAL 
Preamble 
THE STATES PARTIES TO THIS CONVENTION, 
Recognising the right of all States to develop and apply nuclear energy for 
peaceful purposes and their legitimate interests in the potential benefits to be derived 
from the peaceful application of nuclear energy, 
Convinced of the need for facilitating international co-operation in the peaceful 
application of nuclear energy, 
Desiring to avert the potential dangers posed by the unlawful taking and use of 
nuclear material, 
Convinced that offences relating to nuclear material are a matter of grave concern 
and that there is an urgent need to adopt appropriate and effective measures to ensure 
the prevention, detection and punishment of such offences, 
Aware of the need for international co-operation to establish, in confornnty with 
the national law of each State Party and with this Convention, effective measures for 
the physical protection of nuclear material, 
Convinced that this Convention should facilitate the safe transfer of nuclear 
material, 
Stressing also the importance of the physical protection of nuclear material in 
domestic use, storage and transport, 
Recognising the importance of effective physical protection of nuclear material 
used for military purposes, and understanding that such material is and will continue 
to be accorded stringent physical protection, 
Have agreed as follows: 
Article 1 
For the purposes of this Convention: 
a. "nuclear material" means plutonium except that with isotopic concentration 
exceeding 80% in plutonium-238; uranium-233; uranium enriched in the isotope 235 
or 233; uranium containing the mixture of isotopes as occurring in nature other than 
in the form of ore or ore-residue; any material containing one or more of the 
foregoing; 
b. "uranium enriched in the isotope 235 or 233" means uranium containing the 
isotope 235 or 233 or both in an amount such that the abundance ratio of the sum of 
these isotopes to the isotope 238 is greater than the ratio of the isotope 235 to the 
isotope 238 occurring in nature; 
c. "international nuclear transport" means the carriage of a consignment of

68 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
nuclear material by any means of transportation intended to go beyond the territory 
of the State where the shipment originates beginning with the departure from a 
facility of the shipper in that State and ending with the arrival at a facility of the 
receiver within the State of ultimate destination. 
Article 2 
1. This Convention shall apply to nuclear material used for peaceful purposes 
while in international nuclear transport. 
2. With the exception of articles 3 and 4 and paragraph 3 of article 5, this 
Convention shall also apply to nuclear material used for pcacefþul purposes while in 
domestic use, storage and transport. 
3. Apart from the commitments expressly undertaken by States Parties in the 
articles covered by paragraph 2 with respect to nuclear material used for peaceful 
purposes while in domestic use, storage and transport, nothing in this Convention 
shall be interpreted as affecting the sovereign rights of a State regarding the 
domestic use, storage and transport of such nuclear material. 
Article 3 
Each State Party shall take appropriate steps within the framework of its national 
law and consistent with international law to ensure as far as practicable that, during 
international nuclear transports nuclear material within its territory, or on board a 
ship or aircraft under its jurisdiction insofar as such ship or aircraft is engaged in the 
transport to or from that State, is protected at the levels described in Annex 1. 
Article 4 
1. Each State Party shall not export or authorise the export of nuclear material 
unless the State Party has received assurances that such material will be protected 
during the international nuclear transport at the levels described in Annex I. 
2. Each State Party shall not import or authorize the import of nuclear material 
from a State not party to this Convention unless the State Party has received 
assurances that such material will during the international nuclear transport be 
protected at the levels described in Annex I. 
3. A State Party shall not allow the transit of its territory by land or internal 
waterways or through its airports or seaports of nuclear material between States that 
are not parties to this Convention unless the State Party has received assurances as 
far as practicable that this nuclear material will be protected during international 
nuclear transport at the levels described in Annex I. 
4. Each State Party shall apply within the framework of its national law the 
levels of physical protection described in Annex I to nuclear material being 
transported from a part of that State to another part of the same State through 
international waters or airspace. 
5. The State Party responsible for receiving assurances that the nuclear 
material will be protected at the levels described in Annex I according to paragraphs 
1 to 3 shall identify and inform in advance States which the nuclear material is 
expected to transit by land or internal waterways, or whose airports or seaports it is 
expected to enter. 
6. The responsibility for obtaining assurances referred to in paragraph 1 may 
be transferred, by mutual agreement, to the State Party involved in the transport as 
the importing State. 
7. Nothing in this article shall be interpreted as in any way affecting the 
territorial sovereignty and jurisdiction of a State, including that over its airspace and

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 69 
territorial sea. 
Article 5 
1. States Parties shall identify and make known to each other directly or 
through the International Atomic Energy Agency their central authority and point of 
contact having responsibility for physical protection of nuclear material and for coordinating 
recovery and response operations in the event of any unauthorized 
removal, use or alteration of nuclear material or in the event of credible threat 
thereof. 
2. In the case of theft, robbery or any other unlawful taking of nuclear material 
or of credible threat thereof, States Parties shall, in accordance with their national 
law, provide co-operation and assistance to the maximum feasible extent in the 
recovery and protection of such material to any State that so requests. In particular: 
a. State Party shall take appropriate steps to inform as soon as possible 
other States, which appear to it to be concerned, of any theft, robbery or 
other unlawful taking of nuclear material or credible threat thereof and 
to inform, where appropriate, international organizations; 
b. as appropriate, the States Parties concerned shall exchange information 
with each other or international organizations with a view to protecting 
threatened nuclear material, verifying the integrity of the shipping 
container, or recovering unlawfully taken nuclear material and shall: 
i. co-ordinate their efforts through diplomatic and other agreed 
channels; 
ii. render assistance; if requested; 
iii. ensure the return of nuclear material stolen or missing as a 
consequence of the above-mentioned events. 
The means of implementation of this co-operation shall be determined by 
the States Parties concerned. 
3. States Parties shall co-operate and consult as appropriate, with each other 
directly or through international organizations, with a view to obtaining guidance on 
the design, maintenance and improvement of systems of physical protection of 
nuclear material in international transport. 
Article 6 
1. States Parties shall take appropriate measures consistent with their national 
law to protect the confidentiality of any information which they receive in 
confidence by virtue of the provisions of this Convention from another State Party or 
through participation in an activity carried out for the implementation of this 
Convention. If States Parties provide information to international organizations in 
confidence, steps shall be taken to ensure that the confidentiality of such information 
is protected. 
2. States Parties shall not be required by this Convention to provide any 
information which they are not permitted to communicate pursuant to national law or 
which would jeopardize the security of the State concerned or the physical 
protection of nuclear material. 
Article 7 
1. The intentional commission of: 
a. an act without lawful authority which constitutes the receipt, 
possession, use, transfer, alteration, disposal or dispersal of nuclear 
material and which causes or is likely to cause death or serious injury to

70 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
any person or substantial damage to property; 
b. a theft of robbery of nuclear material; 
c. an embezzlement or fraudulent obtaining of nuclear material; 
d. an act constituting a demand for nuclear material by threat or use of 
force or by any other form of intimidation; 
e. a threat: 
(i) to use nuclear material to cause death or serious injury to any 
person or substantial property damage, or 
(ii) to commit an offence described in sub-paragraph (b) in order to 
compel a natural or legal person, international organization or 
State to do or to refrain from doing any act; 
f. an attempt to commit any offence described in paragraphs (a), (b) or (c); 
and 
g. an act which constitutes participation in any offence described in 
paragraphs (a) to (f) 
shall be made a punishable offence by each State Party under its national law. 
2. Each State Party shall make the offences described in this article punishable 
by appropriate penalties which take into account their grave nature. 
Article 8 
1. Each State Party shall take such measures as may be necessary to establish 
its jurisdiction over the offences set forth in article 7 in the following cases: 
a. when the offence is committed in the territory of that State or on board a 
ship or aircraft registered in that State; 
b. when the alleged offender is a national of that State. 
2. Each State Party shall likewise take such measures as may be necessary to 
establish its jurisdiction over these offences in cases where the alleged offender is 
presented in its territory and it does not extradite him pursuant to article 11 to any of 
the States mentioned in paragraph 1. 
3. This Convention does not exclude any criminal jurisdiction exercised in 
accordance with national law. 
4. In addition to the States Parties mentioned in paragraphs 1 and 2, each State 
Party may, consistent with international law, establish its jurisdiction over the 
offences set forth in article 7 when it is involved in international nuclear transport as 
the exporting or importing State. 
Article 9 
Upon being satisfied that the circumstances so warrant, the State Party in whose 
territory the alleged offender is present shall take appropriate measures, including 
detention, under its national law to ensure his presence for the purpose of 
prosecution or extradition. Measures taken according to this article shall be notified 
without delay to the States required to establish jurisdiction pursuant to article 8 and, 
where appropriate, all other States concerned. 
Article 10 
The State Party in whose territory the alleged offender is present shall, if it does 
not extradite him, submit, without exception whatsoever and without undue delay, 
the case to its competent authorities for the purpose of prosecution, through 
proceedings in accordance with the laws of that State.

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 71 
Article 11 
1. The offences in article 7 shall be deemed to be included as extraditable 
offences in any extradition treaty existing between States Parties. States Parties 
undertake to include those offences as extraditable offences in every future 
extradition treaty to be concluded between them. 
2. If a State Party which makes extradition conditional on the existence of a 
treaty receives a request for extradition from another State Party with which it has no 
extradition treaty, it may at its option consider this Convention as the legal basis for 
extradition in respect of those offences. Extradition shall be subject to the other 
conditions provided by the law of the requested State. 
3. States Parties which do not make extradition conditional on the existence of 
a treaty shall recognize those offences as extraditable offences between themselves 
subject to the conditions provided by the law of the requested State. 
4. Each of the offences shall be treated, for the purpose of extradition between 
States Parties, as if it had been committed not only in the place in which it occurred 
but also in the territories of the States Parties required to establish their jurisdiction 
in accordance with paragraph 1 of article 8. 
Article 12 
Any person regarding whom proceedings are being carried out in connection with 
any of the offences set forth in article 7 shall be guaranteed fair treatment at all 
stages of the proceedings. 
Article 13 
1. States Parties shall afford one another the greatest measure of assistance in 
connection with criminal proceedings brought in respect of the offences set forth in 
article 7, including the supply of evidence at their disposal necessary for the 
proceedings. The law of the State requested shall apply in all cases. 
2. The provisions of paragraph 1 shall not affect obligations under any other 
treaty, bilateral or multilateral, which governs or will govern, in whole or in part, 
mutual assistance in criminal matters.
Article 14 
1. Each State Party shall inform the depository of its laws and regulations 
which give effect to this Convention. The depository shall communicate such 
information periodically to all States Parties. 
2. The State Party where an alleged offender is prosecuted shall, wherever 
practicable, first communicate the final outcome of the proceedings to the States 
directly concerned. The State Party shall also communicate the final outcome to the 
depository who shall inform all States. 
3. Where an offence involves nuclear material used for peaceful purposes in 
domestic use, storage or transport, and both the alleged offender and the nuclear 
material remain in the territory of the State Party in which the offence was 
committed, nothing in this Convention shall be interpreted as requiring that State 
Party to provide information concerning criminal proceedings arising out of such an 
offence. 
Article 15 
The Annexes constitute an integral part of this Convention. 
Article 16

72 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
1. A conference of States Parties shall be convened by the depository of five 
years after the entry into force of this Convention to review the implementation of 
the Convention and its adequacy as concerns the preamble, the whole of the 
operative part and the annexes in the light of the then prevailing situation. 
2. At intervals of not less than five years thereafter, the majority of States 
Partics may obtain, by submitting a proposal to this effect to the depository, the 
convening of further conferences with the same objective. 
Article 17 
1. In the event of a dispute between two or more States Parties concerning the 
interpretation or application of this Convention, such States Parties shall consult 
with a view to the settlement of the dispute by negotiation, or by any other peaceful 
means of settling disputes acceptable to all parties to the dispute. 
2. Any dispute of this character which cannot be settled in the manner 
prescribed in paragraph 1 shall, at the request of any party to such dispute, be 
submitted to arbitration or referred to the International Court of Justice for decision. 
Where a dispute is submitted to arbitration, if, within six months from the date of the 
request, the parties to the dispute are unable to agree on the organization of the 
arbitration, a party may request the President of the International Court of Justice or 
the Secretary-General of the United Nations to appoint one or more arbitrators. In 
case of conflicting requests by the partits to the dispute, the request to the Secretary- 
General of the United Nations shall have priority. 
3. Each State Party may at the time of signature, ratification, acceptance, or 
approval of this Convention or accession thereto declare that it does not consider 
itself bound by either or both of the dispute settlement procedures provided for in 
paragraph 2. The other States Parties shall not be bound by a dispute settlement 
procedure provided for in paragraph 2, with respect to a State Party which has made 
a reservation to that procedure. 
4. Any State Party which has made a reservation in accordance with paragraph 
3 may at any time withdraw that reservation by notification to the depositary. 
Article 18 
1. This Convention shall be open for signature by all States at the Headquarters 
of the International Atomic Energy Agency in Vienna and at the Headquarters of the 
United Nations in New York from 3 March 1980 until its entry into force. 
2. This Convention is subject to ratification, acceptance or approval by the 
signatory States. 
3. After its entry into force, this Convention will be open for accession by all 
States. 
4. a. This Convention shall be open for signature or accession by 
international organizations and regional organizations of an integration 
or other nature, provided that any such organization is constituted by 
sovereign States and has competence in respect of the negotiation, 
conclusion and application of international agreements in matters 
covered by this Convention. 
b. In matters within their competence, such organizations shall, on their 
own behalf, exercise the rights and fulfil the responsibilities which this 
Convention attributes to States Parties. 
c. When becoming party to this Convention such an organization shall 
communicate to the depository a declaration indicating which States are

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 73 
members thereof and which articles of this Convention do not apply to 
it. 
d. Such an organization shall not hold any vote additional to those of its 
Member States. 
5. Instruments of ratification, acceptance, approval or accession shall be 
deposited with depository. 
Article 19 
1. This Convention shall enter into force on the thirtieth day following the date 
of deposit of the twenty-first instrument of ratification, acceptance or approval with 
the depository. 
2. For each State ratifying, accepting, approving or acceding to the Convention 
after the date of deposit of the twenty-first instrument of ratification, acceptance or 
approval, the Convention shall enter into force on the thirtieth day after the deposit 
by such State of its instrument of ratification. acceptance, approval or accession. 
Article 20 
1. Without prejudice to article 16 a State Party may propose amendments to 
this Convention. The proposed amendment shall be submitted to the depository who 
shall circulate it immediately to all States Parties. If a majority of States Parties 
request the depository to convene a conference to consider the proposed 
amendments, the depository shall invite all States Parties to attend such a conference 
to being not sooner than thirty days after the invitations are issued. Any amendment 
adopted at the conference by a two-thirds majority of all States Parties shall be 
promptly circulated by the depository to all States Parties. 
2. The amendment shall enter into force for each State Party that deposits its 
instrument of ratification, acceptance or approval of the amendment on the thirtieth 
day after the date on which two-thirds of the States Parties have deposited their 
instruments of ratification, acceptance or approval with the depository. Thereafter, 
the amendment shall enter into force for any other State Party on the day on which 
that State Party deposits its instrument of ratification, acceptance or approval of the 
amendment. 
Article 21 
1. Any State Party any denounce this Convention by written notification to the 
depository. 
2. Denunciation shall take effect one hundred and eighty days following the 
date on which notification is received by the depository. 
Article 22 
The depository shall promptly notify all States of: 
a. each signature of this Convention; 
b. each deposit of an instrument of ratification, acceptance, approval or 
accession; 
c. any reservation or withdrawal in accordance with article 17; 
d. any communication made by an organization in accordance with 
paragraph 4(c) of article 18; 
e. the entry into force of this Convention; 
f. the entry into force of any amendment to this Convention; and 
g. any denunciation made under article 21.

74 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
Article 23 
The original of this Convention, of which the Arabic, Chinese, English, French, 
Russian and Spanish texts are equally authentic, shall be deposited with the Director 
General of the International Atomic Energy Agency who shall send certitied copies 
thereof to all States. 
Sixth Schedule: Annex I 
Levels of Physical Protection to be Applied in International Transport of Nuclear 
Materials as Categorized In Annex II 
1. Levels of physical protection for nuclear material during storage incidental 
to international nuclear transport include: 
a. For Category III materials, storage within an area to which access is 
controlled; 
b. For Category II materials, storage within an area under constant 
surveillance by guards or electronic devices, surrounded by a physical 
barrier with a limited number of points of entry under appropriate 
control or any area with an equivalent level of physical protection; 
c. For Category I material, storage within a protected area as defined for 
Category II above, to which, in addition, access is restricted to persons 
whose trustworthiness has been determined, and which is under 
surveillance by guards who are in close communication with 
appropriate responses forces. Specific measures taken in this context 
should have as their object the detection and prevention of any assault, 
unauthorized access or unauthorized removal of material. 
2. Levels of physical protection for nuclear material during international 
transport include: 
a. For Category II and III materials, transportation shall take place under 
special precautions including prior arrangements among sender, 
receiver, and carrier, and prior agreement between natural or legal 
persons subject to the jurisdiction and regulation of exporting and 
importing States, specifying time,place and procedures for transferring 
transport responsibility; 
b. For Category I materials, transportation shall take place under special 
precautions identified above for transportation of Category II and III 
materials, and in addition, under constant surveillance by escorts and 
under conditions which assure close communication with appropriate 
response forces; 
c. For natural uranium other than in the form of ore or ore-residue; 
transportation protection for quantities exceeding 500 kilograms 
uranium shall include advance notification of shipment specifying mode 
of transport, expected time of arrival and confirmation of receipt of 
shipment. 
Sixth Schedule: Annex II 
Table: Categorization of Nuclear Material 
Material Form 
Category 
I II IIIc/ 
1. Plutoniuma/ Unirradiatedb/ 2 kg or more Less than 2 kg but 
more than 500 g 
500 g or less 
but more than 
15 g

NUCLEAR SAFETY AND RADIATION PROTECTION gS.L.365.15 75 
a All plutonium except that with isotopic concentration exceeding 80% in plutonium-238. 
b Material not irradiated in a reactor or material irradiated in a reactor but with a radiation 
level equal to or less than 100 rads/hour at one metre unshielded. 
c Quantities not falling in Category III and natural uranium should be protected in 
accordance with prudent management practice or work actvity. 
d Although this level of protection is recommended, it would be open to States, upon 
evaluation of the specific circumstances, to assign a different category of physical protection. 
e Other fuel which by virtue of its original fissile material content is classified as Category 
I and II before irradiation may be reduced one category level while the radiation level from the 
fuel exceeds 100 rads/hour at one metre unshielded. 
SEVENTH SCHEDULE 
Protection of workers undertaking intervention 
(1) No worker undertaking an intervention shall be exposed in excess of the 
maximum single year dose limit for occupational exposure specified in the Third 
Schedule except: 
(a) for the purpose of saving life or preventing serious injury; or 
(b) if undertaking actions to prevent the development of catastrophic 
conditions. 
When undertaking intervention under these circumstances, all reasonable 
efforts shall be made to keep doses to workers below twice the maximum single dose 
year limit, except for life saving actions, in which every effort shall be made to keep 
doses below ten times the maximum single dose year limit, in order to avoid 
deterministic effects on health. In addition, workers undertaking actions in which 
their doses may approach or exceed ten times the maximum single dose year limit 
shall do so only when the benefits to others clearly outweigh their owm risk. 
(2) Workers who undertake actions in which the dose may exceed the maximum 
single dose year limit shall be volunteers and shall be clearly and comprehensively 
informed in advance of the associated health risk, and shall, to the extent feasible, be 
trained in the actions that may be required. 
(3) Once the emergency phase of an intervention has ended, workers 
2. Uranium-235 Unirradiatedb/ 
uranium enriched to 20% 
235U or more 
5 kg or more Less than 5 kg but 
more than 1 kg 
1 kg or less 
but more than 
15 g 
uranium enriched to 10% 
235U but less than 20% 
10 kg or more Less than 10 
kg but more 
than 1 kg 
uranium enriched above 
natural, but less than 10% 
235U 
10 kg or more 
3. Uranium-233 Unirradiatedb/ 2 kg or more Less than 2 kg but 
more than 500 kg 
500 g or less 
but more than 
15 g 
4 . I r r a d i a t e d 
fuel 
Depleted or 
natural uranium, 
thorium or lowe 
n r i c h e d f u e l 
( l e s s t h a n 1 0 % 
fossile content)d e 

76 gS.L.365.15 NUCLEAR SAFETY AND RADIATION PROTECTION 
undertakings recovery operations shall be subject to the full system of requirements 
for occupational exposure specified in these regulations. 
(4) All reasonable steps shall be taken to provide appropriate protection during 
the emergency intervention and to assess and separately record the doses received by 
workers involved in such intervention. The doses received during intervention and 
the associated health risk shall be communicated to the workers involved. 
(5) Workers taking part in intervention shall not normally be precluded from 
incurring further occupational exposure because of doses received in an emergency 
situation. However, qualified medical advice shall be obtained before any such 
further exposure, if a worker receives a dose exceeding ten times the maximum 
single dose year limit, or at the worker’s request.

