CHAPTER 188
PROTECTION FROM RADIATION ACT
[SUBSIDIARY LEGISLATION]
INDEX TO SUBSIDIARY LEGISLATION
REGULATIONS
ARRANGEMENT OF REGULATIONS
Regulation
Title
PART I
PRELIMINARY PROVISIONS
1. Citation.
2. Application.
3. Prohibitions relating to use of a building.
4. Duty to ensure safety.
5. Organisation of a radiation monitoring system.
6. Radiation status of individuals.
7. Provisions relating to individual monitoring.
8. Prohibitions relating to working condition A.
9. Individuals in working condition B.
10. Medical surveillance.
11. Provisions relating to radiation accidents.
12. Radiation in working areas.
13. Training of radiation workers.
14. Protective equipment.
15. Provisions relating to working conditions and equipment.
16. Installations.
17. Operating conditions.
18. Reduction of over-exposure.
19. Protection of person in adjacent occupancy.
PART II
PROTECTION AGAINST IONISING RADIATION FROM EXTERNAL SOURCES
20. Protection against ionising radiation from external sources.
21. X-ray equipment and sealed sources.
22. Beam equipment with sealed radioactive sources.
23. Sealed sources used without beam collimation.
24. Unsealed sources.
25. Choice of radioactive material.
26. Choice of working methods and procedure.
27. Design of working places.
28. Use of proper individual protective devices.
29. Laboratory rules.
PART III
SYMBOLS TO INDICATE IONISING RADIATION
30. Requirements for appropriate use of warning signs and signs of devices in radiation area.
31. Labels to be used when transporting radioactive materials.
PART IV
STORAGE OF RADIATION SOURCES
32. Place of storage.
33. Conditions of storage.
34. Storage operations.
PART V
TRANSPORT OF RADIATION SOURCES
35. Transport within licensed premises.
36. Transport within and outside the country.
PART VI
RADIATION MONITORING
37. Radiation monitoring defined.
38. Requirements for monitoring programmes.
39. Monitoring of the working environment.
40. Operational monitoring.
41. Special monitoring.
42. Personnel monitoring.
43. Internal monitoring.
44. Area monitoring.
45. Environmental monitoring.
46. Emergency surveys.
PART VII
RECORD KEEPING AND RELEVANT ACTION
47. Radiation dose records.
PART VIII
DECONTAMINATION
48. Human decontamination.
49. Measures to be taken in case of external contamination of personnel.
50. Decontamination of equipment.
51. Decontamination of working areas and benches.
52. Decontamination of clothing, hospital linen and similar items.
PART IX
RADIOACTIVE WASTE
53. Waste collection.
54. Release of radioactive wastes to the environment.
55. Release of liquid radioactive waste to drains and sewers.
56. Incineration of radioactive wastes.
57. Radioactive waste storage.
PART X
RADIATION ACCIDENTS AND EMERGENCIES
58. Radiation accident.
PART XI
NOTIFICATION OF ACCIDENTS
59. Notification of accidents.
60. Twenty-four hours notification.
61. Reporting of over-exposures and excessive levels of concentration.
62. Notification and report to individuals.
PART XII
VACATING OF THE PREMISES
63. Vacating of the premises.
PART XIII
MISCELLANEOUS PROVISIONS
64. Compliance with regulations.
SCHEDULES
THE PROTECTION FROM RADIATION (CODE OF PRACTICE) REGULATIONS
(Section 40(1))
[1st January, 1991]
G.N. No. 292 of 1990
PART I
PRELIMINARY PROVISIONS (regs 1-19)
1. Citation
These Regulations may be cited as the Protection from Radiation (Code of Practice) Regulations.
2. Application
(1) These Regulations shall apply to–
(a) all users of radiation sources in medicine, veterinary practices, industry, teaching, research, agriculture, hydrology, geology, and other fields of human activity whenever such uses are subject to licensing under the Act;
(b) manufacturers, storekeepers, transporters and disposers of radiation sources and radioactive materials whenever such activities are subjected to registration or licensing under this Act;
(c) all persons who may be exposed to ionising radiation arising from the use of radiation sources and radioactive materials.
(2) Nothing in these Regulations shall apply to any material or use of any material which contains radioactivity of less than 3.7kBq (0.1 microcurie) or if there is no portion on it which the concentration exceeds 74 Bq per gramme (0.002 microcurie per gramme) or material, and other exemptions provided for in section 21 of the Act.
3. Prohibitions relating to use of a building
No person shall put to use a building for the purpose of installation, use of radiation devices or storage of radioactive materials without a compliance certificate or an acceptance certificate in the form set out in the First Schedule.
4. Duty to ensure safety
When the Commission gives a licence, the Management of an establishment shall as part of its responsibility for ensuring protection against ionising radiation, establish an adequate system of radiation monitoring and provide for the services necessary to perform the monitoring operations.
5. Organisation of a radiation monitoring system
When the radiation monitoring system is put in operation details of the duties it entails shall be distributed throughout the organisation, from the Management down to the individual, to the extent appropriate at each level, as indicated under this regulation.
(1) The Management shall–
(a) (i) designate a technically competent person as a Radiation Safety Officer to advise on the development of an appropriate radiation monitoring programme with the establishment, to supervise its performance and to report to the Management the doses received by individuals;
(ii) the Radiation Safety Officer shall also help to advise or seek advice on improvements to protection measures and on the action to be taken if exposure limits have been or are likely to be exceeded;
(b) ensure that there is local supervision of the personnel monitoring system;
(c) develop procedures for the prevention or reduction of exposures;
(d) identify any new factors or charges in processes or procedures that may affect the degree of radiological protection control necessary; and
(e) develop monitoring plans for normal and abnormal radiation situations.
(2) Each worker, after receiving appropriate instructions, shall be responsible for the correct wearing of a dosimeter and for adhering to the procedures established for internal dose determinations.
6. Radiation individuals
(1) Occupational exposure comprises of status of all dose equivalents and committed dose equivalents incurred at work.
(2) The type and extent of individual monitoring required shall depend on the radiation associated with the work.
(3) In order to avoid problems of radiation protection of workers, the Commission in collaboration with the Radiation Protection Officer has set the following system of classification of working conditions–
(a) working condition A which describes conditions where the annual dose equivalents might exceed three-tenths of the relevant annual limits;
(b) working condition B which describes conditions where it is most unlikely that the annual dose equivalents will exceed three-tenths of the relevant annual limits; and if these conditions relate to the eventual possibility or reaching this dose equivalent and not to the dose equivalent actually incurred in a particular year, the classification of working conditions shall be reviewed periodically and whenever changes of programmes are made.
7. Provisions relating to individual monitoring
(1) For any person whose work has been classified as falling under working condition A, individual monitoring is necessary to demonstrate compliance with dose equivalent limits and shall therefore be provided.
(2) For a person whose work falls under condition B, monitoring of the working place is normally sufficient.
(3) Individual monitoring in working condition B may sometimes be performed to confirm that conditions are satisfactory or for the compilation of statistical data on dose distributions.
8. Prohibitions relating to working condition A
(1) No person below the age of 18 and no pregnant woman shall work under radiation condition A.
(2) Workers under this category shall be subject to individual monitoring for external radiation, internal contamination or both.
(3) The radiation status of these workers shall be checked periodically from adequate records of all occupational exposures.
(4) Where a new employee has worked with unsealed radioactive materials in the past (for example in nuclear power plant maintenance) monitoring for internal contamination shall be considered before he commences his new assignment.
(5) Employees who have worked with unsealed sources shall undergo a final monitoring for internal contamination before they terminate employment at an establishment.
(6) When the annual dose equivalent of an individual is likely to approach the limit, additional measures shall be required to show that exposures are within permitted dose limits; and these measures shall include supplemental dosimeter and whole body counting, also it shall be effective to use direct reading devices with adjustable alarm levels, particularly in radiation fields of high dose rates.
9. Individuals in working condition B
(1) Workers in this category shall not normally be subjected to individual monitoring for external radiation and internal contamination.
(2) Monitoring under subsection (1) shall be appropriate for new or revised operations during an initial experimental period to establish that such operations are of a high standard and to confirm that working condition B applies.
(3) Individual monitoring shall also be performed from time to time to confirm that conditions remain satisfactory, or for the compilation of statistical data on dose distributions.
10. Medical surveillance
Every worker under radiation risk shall be made to undergo proper medical examinations as prescribed by the National Radiation Commission Inspector.
11. Provisions relating to radiation accidents
(1) The evaluation of radiation protection shall also include a review of foreseeable types of radiation accidents.
(2) This review shall be done by a Radiation Protection Officer and shall consider the nature and magnitude of foreseeable accidents, the probability of reoccurrence, the consequences and the appropriate preventive measures.
12. Radiation in working areas
Working areas where radiation sources are to be used, stored or disposed of shall be classified according to potential level of exposure as follows–
(a) Restricted Radiation Areas–
where in normal procedures with radiation sources leads to the contamination of surfaces or the air may be extremely hazardous, or where the average dose equivalent rate is known to exceed 0.25 mSv/h. Access to the restricted areas shall be under the strict control of the Radiation Protection Officer who shall define the entry conditions. The restricted area shall be clearly indicated by appropriate area and warning signs;
(b) Controlled Radiation Areas–
where in normal procedures with radiation sources the expected contamination and radiation levels do not exceed 0.25 mSv/h, access to the controlled radiation areas shall be limited to persons who are directly engaged with radiation work. Entry by other persons shall be subject to the consent of the person in-charge of that area. Controlled areas shall be clearly indicated by appropriate area and working signs;
(c) Uncontrolled Areas–
these are areas within the confines of a radiation facility where the external radiation levels are negligible and where radioactive contamination is also not present. In order to avoid uncertainties in the determination of the extent of restricted and controlled areas, the boundaries shall when possible be walls and doors. Inside controlled areas indication shall be made by appropriate signs of the sites where work with radiation sources is carried out.
13. Training of radiation workers
Workers shall be suitably informed of the radiation hazard entailed by their work and the precautions to be taken. This shall require training in safety procedures and effective methods of avoiding unnecessary exposure.
14. Protective equipment
Necessary protective equipment shall be provided and its appropriate use shall be enforced.
15. Provisions relating to working conditions and equipment
Working conditions and equipments shall be reviewed from time to time to ensure that they remain as intended.
16. Installations
Final plans for new installations or for modifications of the existing installations involving structural shielding or other features relevant to protection against external irradiation, shall be approved by the Chief Radiation Protection Officer before building commences. Copies of the plans including specifications relevant to Radiation Protection shall be retained and readily available at the site.
17. Operating conditions
Before any equipment and, or installation where radiation sources are to be used, stored or disposed of, surveys shall be carried out in order to establish that the approved plans have been followed and that the shielding and operating conditions are such that they provide adequate protection against external and internal irradiation for all persons in accordance with the provisions under the Act; and subsequent surveys shall be made after every change in the radiation sources, equipment installations or conditions for use, storage or disposal that may affect the protection and at such intervals as may be necessary to check that satisfactory working conditions are maintained.
18. Reduction of over-exposure
Protection may be achieved by distance, shielding, reduction of exposure time, choice of radiation sources, that is radionuclides, techniques, exposure of manipulating radiation source, establishment and obeyance of appropriate laboratory rules, site of the installations or operations, use of individual protective devices and control of the access to working areas.
19. Protection of person in adjacent occupancy
In calculating the shielding parameters or requirements, steps shall be taken ensure that other persons in the vicinity or adjoining areas are appropriately protected from radiation exposure.
PART II
PROTECTION AGAINST IONISING RADIATION FROM EXTERNAL SOURCES (regs 20-29)
20. Protection against ionising radiation from external sources
(1) In the planning of a radiation installation, account shall be taken of the maximum practicable work load of the equipment.
(2) The shielding of the radiation source and site of the installation in which it is situated shall be such that work may be carried out in compliance with the recommended dose limits for workers and members of the public.
21. X-ray equipment and sealed sources
(1) The exposure outside any auxiliary equipment such as high tension generators shall not exceed 0.2mSv per hour at 5 centimetres from the surface nor 0.02mSv per hour at any readily accessible place within the controlled area. Where the transformer or valve enclosure is located outside the controlled area it shall be necessary to reduce these exposures.
(2) A reliable indication shall be provided at the control panel and when practicable, also readily visible near the radiation beam aperture in order to show whether or not radiation is being generated.
(3) Warning indications shall be so designed so as not to give rise to a false feeling of safety, for example, lights indicating when the tube is not energized may be provided in addition to lights indicating that radiation is being generated; alternatively, lights of the latter type shall be so designed that the equipment cannot be operated if there is a failure of the indicator.
(4) Where the primary beam strikes material, secondary radiation will be generated and attention shall be given to the choice of absorber material and the arrangement of absorbers to minimise the secondary radiation which will include X-rays when electrons or beta particles are absorbed.
(5) High energy accelerators may produce noxious gases and materials (including air and dust) irradiated by the accelerator particles or by the photon beam and may become activated. Expert advice on these problems may be obtained from the Chief Radiation Protection Officer and any necessary safety measures for example choice of material and the installation of forced ventilation, shall be incorporated in the design material that may become activated. Shielding material, machine components, conveyer systems, beam defining systems and sample holders shall be monitored and any appropriate precautions instituted.
22. Beam equipment with sealed radioactive sources
(1) In the design of source housing, consideration shall be given to means whereby the integrity of the source housing is preserved in the event of fire; and information on the location of major radioactive sources shall be readily available to the appropriate fire authorities.
(2) A reliable indication shall be provided at the control panel and, when practicable, also at the source housing, in order to show when the source is in the ON position. There shall also be an indication capable of showing when the source is in the OFF position. Appropriate signs shall be displayed outside the irradiation room.
(3) The surface of the housing of the source capsule, particularly the beam aperture, together with any other locations likely to be contaminated in the event of a leakage, shall be tested for leakage or radioactive material at least once a year.
23. Sealed sources used without beam collimation
(1) A sealed source is considered to be any radioactive substance sealed in an inactive container or capsule, or bonded wholly within an inactive material, so as to prevent dispersion of the radioactive substance during routine use. It shall be noted that many sealed sources are fragile and may easily be damaged with consequent release of radioactive material. A sealed source may normally be regarded as exempted from these recommendations if it consists not more that 3.7 x 10>
(2) Sealed sources containing activities exceeding those specified in subregulation (1) of this regulation, will need to be recognisable. Hence, whenever practical, all such sources shall be readily recognisable as being radioactive and the source container, capsule or bonding shall be labelled in such a way that the source can be identified; and if practicable, the nature and activity or the radioactive material shall be marked directly on the label, which shall be fire resistant.
(3) Actual or suspected loss of, or damage to, a sealed source shall be reported immediately to the person responsible for radiation safety within the facility.
(4) Local rules for the users' area shall be prepared detailing the manner of use of sealed sources and the procedure to be adopted in the event of loss of, damage to, or accidents involving a sealed source. In preparing such rules, consideration shall be given as appropriate, to factors such as possible cause of loss, spread of contamination, effect of fire, identification and treatment of causalities. A copy of local rules shall be sent to the Chief Radiation Protection Officer.
(5) When not in use, sealed sources, shall be stored under conditions which provide adequate protection for those entering and in adjacent areas to the store, security against unauthorised removal and minimum risk due to fire and flood. Where sources are liable to release radioactive gases or vapours, the store shall, if necessary, be mechanically ventilated to the outside air. Such ventilation may need to be continuous for an appropriate period before and whilst the store is open depending upon the activity and of radiotoxicity of the radionuclide concerned.
(6) Sealed sources shall be tested for leakage at appropriate intervals and at least once every year.
(7) Wherever there are reasonable grounds for believing that a sealed source is, or is liable to be leaking, it shall be hermetically sealed in a suitable container pending repair by the manufacturer or by a competent establishment. In such circumstances the area in which the source has been used and any person having used it shall be checked for contamination.
(8) In order to ensure the minimum irradiation of personnel engaged in preparation or application of sources, appropriate handling tools or implant instruments shall be used at all times. These tools shall be constructed so as to provide the maximum handling distance compatible with effective manipulation. All operators shall have adequate training, for example, with dummy sources, in these manipulative procedures; and whenever practicable remote means of manipulation which ensure adequate protection of staff, shall be used.
(9) An encapsulated source intended for the utilisation of beta radiation requires a thin window. This window and its mounting shall be so constructed as to minimise the risk of leakage of radioactive material and when not in use shall be covered by a shield of sufficient thickness to absorb all the beta radiation. When the window is being cleaned, or the source tested for leakage, care shall be taken to avoid damaging the window.
(10) It is understood that all beta sources emit bremsstrahlung and may cause other types of penetrating radiation such as X-rays, annihilation radiation and characteristic X-rays. Possible exposure from such radiation shall be evaluated and the necessary precautions taken.
(11) In the case of work that is undertaken outside fixed installations (for example mobile site radiograph) temporary barriers and warning signs to restrict access to the controlled area shall be used when necessary. Further information with regard to shielding of radiation sources will be given by the Chief Radiation Protection Officer.
24. Unsealed sources
(1) The provisions of regulation 23 of this Code of Practice relating to sealed sources shall be applied also to unsealed sources wherever appropriate.
(2) In dealing with unsealed sources special attention shall be paid to internal radiation hazards, for example, contamination, skin penetrations, ingestion or inhalation which shall be considered in addition to the usual radiation hazard of sealed sources. The extent of the protective measures to be taken will depend upon total activity, the specific activity, the radiotoxicity, the chemical and physical properties of the radionuclides or radioactive compounds.
25. Choice of radioactive material
When a choice between several radionuclides of varying toxicities is possible, the one with relatively low toxicity shall be used, and for this the Chief Radiation Protection Officer shall be consulted.
26. Choice of working methods procedure
(1) Good working procedures are so important that techniques shall be well thought out and understood before work is undertaken; and and these procedures shall be tried out in practice runs with inactive material so that when radioactive material is used, operations are performed speedily and confidently with minimum exposure and risk of accident; the working procedures shall be reviewed by the Radiation Protection Officer.
(2) The working methods shall be studies and procedures adopted to avoid as far as possible the dispersal of radioactive material, in particular through the formation of aerosols, gases, vapours or dust; and in addition, wet operations shall be planned to limit the spread or dispersal of radioactive materials and all unnecessary movement of persons or materials shall be avoided.
27. Design of working places
(1) The design of work places where unsealed radioactive materials are to be used, shall be aimed at minimising the release of radioactive material and waste into the working environment and at controlling and minimising the spread of radioactive material and waste into the environment; and to achieve these objectives all working places and laboratories belonging to restricted and controlled areas shall be classified in accordance with the following table–
Table 1. Limitation of activities in various types of working places or laboratories.
Radiotoxicity of radionuclides | Minimum significant quantity (x10Bq) | Type of working place |
||
Type C | Type B | Type A |
||
Very high | 0.37 | 3.7 | 0.037 - | 3.7 |
High | 3.7 | 37.0 | 0.37 - | 37.0 |
Moderate | 37.0 | 370.0 | 3.7 - | 370.00 |
Low | 370.0 | 3700.0 | 37.0 - | 3700.0 |
Modifying factors may be applied to the quantities indicated in the last three columns of the table according to the complexity of the procedures to be followed. The following factors are suggested, but due regard shall be paid to the circumstances affecting individual cases–
Procedure-Modifying factor | ||
Storage (stock solutions) | x | 100 |
Very simple wet operations | x | 10 |
Normal chemical operations | x | 1 |
Complex wet operations with (risk of spill) | x | 0.1 |
Simple dry operations | x | 0.1 |
Dry and dusty operations | x | 0.01 |
(2) The type "C" laboratory is a slightly modified modern conventional chemical laboratory having floors covered with linoleum or similar non-porous material, work benches with non-absorbent top surfaces, at least one good fume hood with induced draught, working surfaces including fume hood strong enough to carry any necessary shielding, the exhaust-air carried outside the building but need not be filtered.
The type "B" laboratory is a specialised radioisotope laboratory designed so as to minimise the incidence and spread of the contamination, as well as to enable rapid and easy decontamination.
The type "A" laboratory is a highly specialised laboratory for handling large quantities of radioactive materials and shall be designed and constructed by a competent organisation or enterprise and approved by the Chief Radiation Protection Officer.
(3) Appropriate changing room facilities shall be provided, where necessary, at the entrance to the controlled radiation area for the workers to change into the required protective clothing. Such facilities shall provide separate lockers for personal protective clothing and adequate facilities for washing of hands, and appropriate personnel monitoring equipment. Emergency shower facilities shall also be provided where appropriate. The changing room shall have an appropriate demarcation barrier between radioactive and non-radioactive areas.
(4) When the contamination level cannot be maintained below the required level, individual protection shall be provided in the form of air-line hoods or positive pressure masks. In cases where the use of air-line protective equipment is not practicable, special filter type respirators shall be used. Such respirators shall be of the type approved by a recognised laboratory test for the class of service required, and the practical safe limits of use shall be known and observed. The respirators shall be capable of standing up to the conditions of use and shall be checked and tested periodically. They shall be individually fitted and tested for adequacy of fit. Users of respirators shall accustom themselves to the discipline necessary in their use, otherwise harm may be done by introducing contamination under the face piece.
28. Use of proper individual protective devices
(1) Protective clothing appropriate to the radioactive contamination and associated risks shall be worn by every person in a controlled area even if only small quantities of radioactive materials are to be used. The type of protective clothing required depends upon the amount of radioactivity. The handling of even trace amounts will require laboratory coats over normal attire. When large quantities of radioactivity are handled, overalls or other clothing that completely cover the body shall be worn. The use of such clothing shall be restricted to the operational areas only. In such operation the risk of contamination may also require the use of special shoe coverings or the provision of shoes for use only in controlled or restricted areas.
(2) In type "C" working places, workers shall wear simple protective clothing such as ordinary laboratory or surgical coats. In type "A" or "B" working places protective clothing and devices shall be provided according to the nature of the work. The protective clothing for use in controlled radiation areas shall be clearly identified, for example by different colours and shall not in any case be worn outside the controlled areas. In addition, protective clothes and personal clothes shall be kept in separate cubicles or change rooms. When changing protective clothing care shall be taken to avoid contamination risks.
(3) Rubber, polyvinyl chloride and gloves shall be worn when working with unsealed radioactive substances to protect against contamination of the skin.
29. Laboratory rules
The Radiation Protection Officer shall be responsible for providing a set of general laboratory rules which shall be observed when handling unsealed radioactive sources. The rules shall include the following–
(a) eating, drinking, smoking and the use of cosmetics are strictly prohibited in controlled and restricted radiation areas;
(b) each person, when in a controlled or restricted radiation area, shall make proper use of the individual protective devices that are provided for his protection;
(c) pipetting or the performance of similar operations by mouth suction is strictly prohibited, and glass blowing shall be done by special techniques which avoid blowing by mouth;
(d) all work with radioactive materials shall be performed over easily decontaminable trays, the bottom of which shall be covered with absorbent paper;
(e) all operations involving volatile materials heating or digestion shall be carried out under a properly designed fume hood with an air velocity at the hood face of not less than 0.5m per sec.
(f) any operation in which particulate activity or radioactive dust may arise shall be carried out in a closed and adequately sealed glove box; and
(g) any accident involving radioactive materials shall be immediately reported to the Radiation Protection Officer.
PART III
SYMBOLS TO INDICATE IONISING RADIATION (regs 30-31)
30. Requirements for appropriate use of warning signs and signs of devices in radiation areas
The requirements for appropriate use of warning signs and signs of devices in radiation areas are given in the following Table 2–
Table 2. Requirements for appropriate use of warning signs and signs of devices in a radiation area.
Area of | Radiation | Cautioning | Additional |
|
| (danger) |
|
|
| (danger) | Direct reading devices with adjustable alarm levels to warn presence of radiation fields of high dose rates |
|
| (danger) | Same as above if area is also of high radiation |
Entrance to areas/rooms in which radioactive materials are used or stored in an amount exceeding ten times the amount of derived concentration limits. | Yes | (danger) Radioactive material(s) and where practical, describe the quantities and kind of radioactive materials involved. | None |
Radiation | Yes | (danger) | Label placed on the control panel |
In case of X-ray machine only | Yes | (danger) |
III. SYMBOLS TO INDICATE IONISING RADIATIONS
III. 1 The basic symbol is of the design shown in figure 1.
The symbol should be supplemented with a text with information of the nature of the risk (e.g."radioactive materials").
III. 2 The symbol shall be in black colour and shall be placed on yellow or white background.
III. 3 This symbol shall be used on labels, warning signs, tags, etc. When such symbols are used to indicate the presence of radiation sources, appropriate inscriptions may be used with it.
FIG. 2. Category I - WHITE label. The background colour of the label shall be white, the colour of the trefoil and the printing shall be black, and the colour of the category bar shall be red.
FIG. 3. Category II - YELLOW Label. The background colour of the upper half of the label shall be yellow and of the lower half white, the colour of the trefoil and the printing shall be black, and the colour of the category bars shall be red.
FIG. 4. Category III - YELLOW Label. The background colour of the upper half of the label shall be yellow and the lower half white, the colour of the trefoil and the printing shall be black, and the colour of the category bars shall be red.
31. Labels to be used when transporting radioactive materials
Labels to be used when transporting radiative materials in accordance with these rules are given in figures 2, 3, and 4 for packages containing radiation sources dependent upon the category of the radioactive materials and, in figure 1, for vehicles transporting radiation sources.
PART IV
STORAGE OF RADIATION SOURCES (regs 32-34)
32. Place of storage
(1) When not in use radiation sources shall be kept in a place of storage assigned for this purpose only, bearing the appropriate warning symbol.
(2) The place of storage shall be adequately shielded such that at the outside surface of its walls or containment the radiation dose shall not exceed 01 mSv per hour, and shall be chosen so as to minimise risks from fire or flood.
(3) The place of storage shall be adequately secured with a lock to guard against unauthorised access. The key or keys for the store shall be held and controlled by an appropriate responsible person nominated for this purpose.
(4) The place of storage shall be inspected regularly and checked for possible contamination.
(5) The place of storage shall be sited and designed so as to ensure that both during storage and in the course of transfer of radiation sources to and from the store, the sources do not give excessive exposure to any person.
(6) If the place of storage is to contain either sealed or unsealed radiation sources that are liable to release a radioactive gas or vapour the store shall be continuously vented to the open air, or provided with a mechanical venting system that can be operated from outside the store before the store is opened.
33. Conditions of storage
(1) All radiation sources shall be clearly labelled, giving information on their activity and nature.
(2) The containers for beta emitting radionuclides shall have adequate thickness to reduce the primary radiation to a safe level. Considerable bremsstrahlung may arise from high intensity sources and additional shielding shall be provided if necessary.
(3) Gamma emitting and neutron sources shall be stored in such a way as to limit the radiation exposure from the other sources when any one source is being handled.
(4) Appropriate equipment shall be provided for storing unsealed radiation sources to prevent only external irradiation hazards but also internal contamination hazards.
(5) In type "C" working places the sources shall be stored in special cupboards providing adequate protection and security against unauthorised access.
(6) In type "B" working places a special secure receptacle shall be used which provides adequate protection that can be ventilated if necessary, and also provides security against unauthorised access.
34. Storage operations
(1) Records shall be kept of all stored radiation sources. These records shall give clear information on the type of source activity, times of removal and return, and the name of the person responsible for the source during its absence from the store.
(2) Inventories shall be taken periodically.
(3) Thermally unstable solutions containing radioactive material in citric acid or other oxidizing solutions containing traces of organic material, alpha activity in excess of 9 x 10>
(4) Solutions having a high activity (in excess of 3.7 x 10>
(5) Bottles containing radioactive liquids shall be placed in non-fragile vessels large enough to hold the entire contents of the bottles in case of breakage.
PART V
TRANSPORT OF RADIATION SOURCES (regs 35-36)
35. Transport within licensed premises
(1) The competent person or Radiation Protection Officer identified at the establishment shall be responsible for the precautions to be taken in the movement of radioactive substance from one area to another within the establishment.
(2) Radioactive substances shall be transported within the licensed premises only in containers provided for the purpose and should properly be labelled. Such containers shall be designed–
(a) to provide adequate protection for all persons during loading, transport and unloading (type "A"); and
(b) to prevent loss of radioactive material and to minimise the risk of spilling unsealed radioactive sources (type "B");
(c) radioactive materials may be moved within the establishment in packing intended for transport outside the establishment.
36. Transport within and outside the country
(1) Transport may be by road, rail, and air or sea. Licence for the transportation outside shall be issued by the Commission.
(2) Packaging of radiation sources shall try be designed so as to provide the necessary shielding against ionising radiations and to adequately prevent loss and spillage of radioactive materials during transport operation in case of transport accidents.
(3) According to radiation levels, packages containing radiation sources are placed in one of the following three categories–
(a) Category I - White.
The radiation level originating from the package at any time during normal transport shall not exceed 5 mSv per hour at any location on the external surface of the package.
(b) Category II - Yellow.
The radiation level originating from the package at any time during transport shall not exceed 0.5 mSv per hour at any location on the surface of the package, and 0.10 mSv per hour measured at one metre from the external surface of the package.
(c) Category III - Yellow.
The radiation level originating from the package at any time during transport shall not exceed 2 mSv per hour at any location on the external surface of the package and 0.1 mSv per hour measured at one metre from the external surface of the package.
(4) Depending on the quantity of radioactive materials contained in it, the package may be of type "A" or "B".
(5) The loose radioactive contamination on any external surface of the package shall be kept as low as practicable and shall not exceed the values given in table 3 below:
Table 3. Maximum Permissible Level (MPL1) of loose contamination on packages.
CONTAMINANT | MPL2 (Bq/Sq.cm) |
U-nat, U-depleted and Th-nat | 37.00 |
Beta and gamma emitters and low toxicity alpha emitters 3 | 3.70 |
All other alpha emitters | 0.37 |
(6) When transporting radiation sources, care shall be taken that persons involved are not exposed to ionising radiation in excess of the limits given in the second Schedule.
(7) All packages containing radiation sources shall be separated from undeveloped photographic films or plates so that these are not exposed to more than 10 mSv.
(8) Packages of radioactive materials shall be stored in separate transit areas for as short a time as practicable and far from other hazardous materials.
PART VI
RADIATION MONITORING (regs 37-46)
37. Radiation monitoring defined
(1) Monitoring is the general term used for all measures related to the assessment of exposure to ionising radiation arising from external and internal radiation sources.
(2) Monitoring programmes shall be designed to meet clearly defined objectives and these shall be recorded. The design of monitoring programme must include the basis of interpretation in relation to the objectives. This basis shall be recorded. Finally, the design shall incorporate guidance on what records are necessary and on the associated record-keeping and record-destruction procedures.
38. Requirements monitoring programmes
The following monitoring programmes shall be designed–
(1) Monitoring of work places. It is convenient to subdivide the monitoring of work places into three distinct types:
(a) monitoring of working environment;
(b) operational monitoring;
(c) special monitoring.
(2) Personnel monitoring.
(3) Environment monitoring.
39. Monitoring of the working environment
(1) This is intended to show that the working environment is satisfactory for continued operations and that no change has taken place calling for a reassessment of operating procedures. It is largely of a confirmatory nature but may not include the use of fixed detectors to identify the on set of abnormal or emergency conditions. The inspections and licensing section of the National Radiation Commission shall carry out the measurement on request.
(2) The most important part of the programme of monitoring for external radiation in the work places is the conduct of a comprehensive survey when any new installation is put into service or when any substantial changes have been made, or may be made, in an existing installation.
(3) If the radiation situation in a work place is not liable to change, except as a result of substantial alteration to the protective equipment or the processes carried out in the work place (which shall be followed by comprehensive surveys), then routine monitoring of the working environment is not necessary. If, however, the radiation fields in the work place are liable to change, but the changes are not likely to be rapid or severe, then occasional checks, mainly at fixed points, shall be carried out and will usually give sufficient warning of deteriorating conditions. Alternatively, the results of personnel monitoring for external radiation may be used for this purpose. If the radiation fields are liable to increase rapidly to serious levels, then a system of warning instruments shall be installed at fixed points in the working area or be worn individually by the workers. It is particularly important to identify situations calling for this type of warning systems because if carried out effectively, it can prevent exposure to high doses of radiation and thus eliminate a dangerous situation.
(4) The control of contamination in operations with unsealed radioactive materials requires a succession of defensive barriers, that is, the principle of defence in depth. The material shall be confined so far as is practicable at the point of use by the adoption of appropriate working procedures but there may be some degree of spread away from this point and the working place itself is regarded as a subsidiary part of the overall containment.
(5) The principal objectives of a programme of monitoring for surface contamination can be summarised as follows–
(a) to detect failure of containment;
(b) to detect departures from good operating procedures;
(c) to limit surface contamination to levels at which the general standards of good house keeping are adequate to avoid exposures to radiation approaching the recommended standard and;
(d) to provide information for the planning of programmes for additional personnel monitoring and air monitoring, and for defining improved working procedures;
(e) monitoring of the working environment for air contamination will rarely be needed on a routine basis except in the following circumstances–
(i) where gaseous or volatile materials are handed in big quantities, for example, tritium and its compounds in large scale production processes, the oxide in heavy water reactors, and iodine isotopes at levels of a few hundred millicuries);
(ii) the handling of any radioactive material (including reactor fuel fabrication and reprocessing, and the machining of natural and enriched uranium) in conditions of frequent and substantial contamination of work places;
(iii) the processing of plutonium and other transuranium elements; and
(iv) uranium mining, milling and refining.
40. Operational monitoring
(1) Operational monitoring is intended to provide a check on a particular operation and give, if necessary, a basis for immediate decisions on the conduct of the operation. It is particularly appropriate in the control of short term procedures under conditions which will be unsatisfactory for continued long term use.
(2) The design of an operational monitoring programme depends greatly on whether the operations to be carried out influence the radiation fields or whether these will remain substantially constant throughout the operations. In the latter case a preliminary survey of the radiation dose rate in the region to be occupied by the workers shall be carried out and will usually be sufficient, though this may have to be repeated before each series of operations. If the operations themselves influence the dose rates then a continued series of measurements shall be made throughout the operation. The detailed design of such a survey must depend critically on the form of operation and on the conditions under which it takes place.
41. Special monitoring
Special monitoring shall be carried out in the working environment when insufficient information is available to achieve adequate control, or when an operation is being carried out either for the first time or in abnormal circumstances.
Special monitoring is intended to provide more detailed information in order to determine the problems and to define future procedures. Any programme of special monitoring shall therefore have a limited duration and clear cut objectives and give way to appropriate monitoring of the working environment or operational monitoring once the objectives have been achieved.
42. Personnel monitoring
(1) Personnel monitoring is the making and interpreting of measurements made by equipment carried on an individual worker or measurements made of the activity in their bodies or excreta.
The primary purpose of such monitoring is to obtain an estimate of the total dose or dose commitment to selected organs and tissues, and to discover accidental exposures. For routine monitoring, the period of interest extends over months or years.
If the doses are well below the relevant dose limits, the upper limit rather than the actual value of the dose will be sufficient, for example by use of investigative levels. Where personnel monitoring is not practicable for some types of exposure for example intermediate energy neutrons from radon, thoron, thorium and their daughters, special programmes of monitoring the work places shall have to be instituted to provide estimates of doses or intakes concerned.
(2) The Personnel monitoring for external radiation is carried out by the Radiation Protection Services department of the National Radiation Commission, using Thermoluminescent Dosimeters. The dosimeters are used by radiation workers for one month on the upper left part of the chest and after this period are sent back for evaluation. The results of personnel dose measurements are sent to the appropriate Radiation Safety Officers. The licence for the use of radiation sources is conditional upon the introduction of personnel dosimetry for all workers who are under risk of irradiation.
(3) The results of personnel monitoring shall be used to give information about the conditions in the work place and, which methods of personnel monitoring are cheap and easy to interpret. This will often provide a simple way of establishing whether the general conditions in the work place are under satisfactory control.
(4) All radiation workers shall be under medical supervision. Where any person has received a radiation dose in excess of the recommended standards (Second Schedule) the Chief Radiation Protection Officer shall decide whether or not to carry out a medical examination of the person, or such other investigation as may be indicated, and arranged for appropriate medical treatment where necessary. The Chief Radiation Protection Officer shall also determine whether he may continue his work or shall be suspended from it, shall determine the period of any suspension.
43. Internal monitoring
Programmes of monitoring for internal contamination are usually costly in scientific and technical manpower, and it is therefore important that the selection of workers to be monitored shall be appropriate. Experience has shown that routine individual monitoring for internal contamination will rarely be needed. The National Radiation Commission inspector together with the Radiation Safety Officers shall decide whether or not such measurement is needed.
44. Area monitoring
The assessment of doses in minor accidents is usually adequately covered by means of regular dosimeters for individual monitoring. The likelihood and probable magnitude of these events can be noted on the dosimeters. In some circumstances, severe exposures are possible though very unlikely. Two typical situations are–
(a) operational errors or equipment failure may occur when large amounts of radioactivity are being transferred within or between shields;
(b) failure of interlocks may occur with high dose-rate equipment such as X-ray sets or accelerators. The Radiation Safety Officer shall be responsible for such measurements.
45. Environmental monitoring
Environmental monitoring means the measurement of radiation and radioactivity outside boundaries of installations handling radioactive materials or radiation sources, and shall include measurements made necessary by the operation of these installations. Monitoring of the process and of the release of waste are closely connected with any environmental monitoring programme and, for the great majority of installations, provide efficient information to make environmental monitoring unnecessary. The environmental monitoring programmes shall be carried out by the National Radiation Commission.
46. Emergency surveys
Emergency surveys may be needed around any installation handling sufficiently large amounts of radioactive materials to constitute a potential hazard to people outside the installation. Such surveys may also be required following accidents in the transportation of radioactive materials. The Chief Radiation Protection Officer will decide if such surveys will have to be done.
PART VII
RECORD KEEPING AND RELEVANT ACTION (reg 47)
47. Radiation dose records
(1) The licensee shall arrange for the following records to be kept, where relevant–
(a) radiation dose records;
(b) cases of overexposure;
(c) transfer records;
(d) medical records;
(e) cases of contamination of skin, hair and clothing;
(f) area monitoring;
(g) calibration of monitoring instruments and dose rate meters;
(h) alteration of output or quality of radiation as a result of modification or maintenance of the source;
(i) tests of individual protection devices;
(j) leakage tests of sealed radioactive sources;
(k) administration of permanent implants;
(l) list of all sealed radiation sources in stock with dates of receipt;
(m) list of all sealed radiation sources issued from and returned to the store, with appropriate dates and signatures of users;
(n) stock of unsealed radioactive materials, with dates of receipt, issued and disposal;
(q) investigation of emergencies and accidents; and
(r) disposal of radioactive wastes.
(2) The radiation dose records shall be established for every worker in accordance with Part V of this Code. The record shall show the doses, both from external and internal radiation sources, received as a result of previous work with ionising radiation, and doses received in any one year and last thirteen consecutive weeks. Emergency and accident doses shall also be noted on the record. These records shall be retained for a period of thirty years after the last record.
(3) The transfer record is the summary of the radiation dose record issued to worker terminating the employment. The worker shall produce this record when taking a new work involving exposure to ionising radiation. The transfer record shall be retained for thirty years after date of issue.
(4) The medical records shall contain results of all medical examinations (employment, routine and after emergency or accidental exposures) for the workers in the course of his employment. These records shall be retained for thirty years after the last entry.
(5) All contaminations of the skin, head and clothing which cannot be reduced by first aid measures to a level below the maximum permissible contamination levels given in the Radiation Protection Standard shall be recorded. This record shall be attached to the medical record and retained for two years. The records shall indicate the case of contamination, the action taken to deal with it and the length of time during which the excess contamination lasted.
(6) Area monitoring results shall be recorded for future reference.
(7) Calibration records shall contain the results or calibration, date when calibration was performed and data about any repair or maintenance work done on the instrument. These records shall be retained for two years after last entry.
(8) Any action that will permanently change the output or quality of radiation shall be recorded in detail.
(9) All individual protective devices whose characteristics or readiness for use may change with time shall be tested at intervals of six months and the results of tests recorded.
(10) All tests of sealed radiation sources for leakage shall be recorded, showing dates and results of the tests.
(11) All administration to patients of permanent implants shall be adequately recorded.
(12) Receipt of all sealed radiation sources shall be recorded, showing dates and also the date of disposal or transfer to another licensee.
(13) If there is a main store for sealed sources the issue and return of them to the store shall be recorded together with the place of use and the name of the users. If necessary a responsible person may be appointed in charge of the stock of sources.
(14) All administration to patients of unsealed radioactive materials shall be properly recorded.
(15) All treatment and diagnosis using ionising radiation shall be recorded and the records be readily available for transfer from one hospital to another.
(16) All unsealed radioactive materials in stock, their issuance; and eventual return to the store as well as the purpose of issuance and recipient, shall be recorded. If necessary a person may be nominated for dispensing the unsealed radioactive materials.
(17) Investigation of emergencies and accidents, and the corresponding conclusions shall be recorded in detail for future reference.
PART VIII
DECONTAMINATION (regs 48-52)
48. Human decontamination
Measures to be taken in case of internal contamination of personnel. Internal radioactive contamination of personnel can result from ingestion, inhalation, or penetration of the skin through a wound. If internal contamination is suspected as a result of an accident during work, it should be immediately reported to the person responsible for radiation protection. Internal contamination is essentially a medical problem, parallel in some ways to the absorption of chemical toxins. Any special corrective procedures needed should therefore the carried out in combination with normal medical attention and under medical advice and supervision, and shall be reported in writing to the Chief Radiation Protection Officer (CRPO).
49. Measures to be case of external taken in contamination of personnel
(1) External contamination of a person can be a hazard in three ways–
(a) it may cause injury from local exposure of skin;
(b) it may penetrate the intact skin (particularly in the presence of certain organic solvents);
(c) it may eventually be transferred into the body by ingestion or inhalation.
(2) The danger of loose activity being eventually carried into the body is often the most critical hazard, hence decontamination procedures are primarily concerned with loose contamination.
(3) As a rule except for decontamination of the hands or in cases of emergency as agreed upon by the person responsible for radiation protection, all mild decontamination procedures described in subregulations (4) and (5) of this regulation should be carried out under the supervision of the person responsible for radiation protection. Attempts to remove contamination which resists mild procedures should be made only under medical supervision.
(4) The immediate washing of contaminated areas with water and soap is the method of choice for removing loose contamination subject to the following elementary precautions–
(a) tepid water shall be used;
(b) the soap shall not be abrasive nor highly alkaline;
(c) washing can be helped by scrubbing with a soft brush, but only in such a way as not to ablaze the skin; and
(d) the skin shall be washed for a few minutes at a time, then dried and monitored. Washing can be repeated if necessary (as indicated by monitoring) provided that there is no indication of damage to the skin.
(5) If these procedures fail, mild detergent approved by persons responsible for radiation protection may be used, although repeated applications of detergent to the same area of the skin (for example hands) might injure it and make it penetrable. The use of organic solvents or acid or alkaline solutions shall be avoided.
(6) Special attention shall be paid to proper contamination of creases, folds, hair and such parts of the hands as finger nails, interfinger spaces and the outer of the hands.
(7) Care shall be taken to avoid as far as possible the spread of the contamination to uncontaminated parts of the body and to avoid internal contamination. If there is a risk of such spread, an attempt shall first be made to remove the contamination with absorbent material, if necessary, adequately covering at the same time the adjacent non-contaminated areas of the skin. In general an open wound shall be protected against any additional contamination by decontamination procedures applied to other areas.
(8) After each decontamination operation, the treated place shall be dried with fresh non-contaminated towels and swab, and monitored; and all towels and swabs so used shall be treated as contaminated materials.
(9) While decontaminating the face, special care shall be taken not to contaminate the eyes or lips.
(10) Decontamination of eyes shall be undertaken immediately. Not only is the radionuclide to be considered but also the chemical nature of the contaminant and possible complication due to the foreign bodies and mechanical or chemical irritants. Additional irradiation of the eyes by decontamination procedures shall be avoided. Immediate irrigation of the eyes with copies amount of water or with appropriate approved chemical solutions is recommended. These solutions and a suitable vessel for eye washing shall be provided as first-aid kit. After this first procedure every case of contamination of the eyes shall be submitted to medical control and further treatment.
(11) Attempt to remove contamination which resists washing shall only be made under medical supervision.
50. Decontamination of equipment
A decision to decontaminate equipment must take into account the continuing value of the equipment compared with the risks and cost of decontamination, and the cost of disposal or radioactive waste.
(1) Decontamination methods for equipment are of two kinds–
(a) removal of contamination without damage of the surface below;
(b) removal of the surface of the equipment together with the adhering contamination.
In all cases the first method shall be used initially and only if several attempts fail shall the second method be tried since damaged surfaces may be unsuitable for reuse because of the tendency to collect contamination easily.
(2) Where the half-life of the contaminating radionuclide is short, it may be desirable to store the equipment for decay of activity rather than to attempt decontamination.
(3) Decontamination of equipment shall generally be done as soon as possible after its use; and in many cases this will prevent the contaminant from becoming fixed and from being ultimately more difficult to deal with. It will often be found that surfaces that have been kept moist are easier to clean.
(4) The cleaning of contaminated glassware and other tools shall be done with great care by informed persons in a well ventilated hood set aside in the laboratory for that purpose, or special decontamination areas.
(5) If it is necessary to dismantle any equipment before decontamination procedures, careful monitoring shall be carried out during the operation.
51. Decontamination of working areas and benches
(1) As soon as possible after contamination of working areas, benches, tables, et cetera, has occurred or has been detected, decontamination shall be carried out by suitably equipped and informed personnel.
(2) All surfaces shall be cleaned by wet methods if possible as the use of dry methods may create a dust hazard.
52. Decontamination of clothing, hospital linen and similar items
(1) In any handling of contaminated clothing, appropriate precautions shall be taken to control external exposure and also to prevent or control contamination of the worker and of the surrounding areas by the formation of aerosols; and all contaminated clothing, hospital linen and similar items shall be placed in suitable plastic bags which shall then be sealed and labelled with the appropriate symbol and information as to its origin and type of contamination.
(2) Contaminated clothing or bedding must not be sent to public laundries unless the activities, averaged over an area not exceeding 100 sq. cm, are everywhere below the maximum permissible contamination levels.
(3) In the case of short-lived radioactive contamination, storage is normally recommended until the activity has reduced to safe levels.
(4) It will usually be desirable to wash contaminated clothing in specially designed laundry facilities and the area where decontamination is carried out be monitored. Personnel working in these facilities shall be provided with dosimetry badges.
(5) Rubber gloves and other rubber goods and plastics are usually decontaminated readily. Such items shall first be washed using ordinary laundry formula. If this does not prove effective, rubber items can be washed in dilute nitric acid or other detergents chosen according to the nature of the contamination. This shall be followed by washing using scouring powder in running tap water.
(6) If the clothing, linen, et cetera cannot be decontaminated to a safe level it shall be treated as radioactive waste.
PART IX
RADIOACTIVE WASTE (regs 53-57)
53. Waste collection
(1) Suitable receptacles for waste shall be available in all working places where radioactive waste may originate.
(2) Solid waste shall be deposited in refuse bins with foot-operated lids. The bins shall be lined with removable plastic or paper bags to facilitate removal of the waste without contamination.
(3) If no licensed facilities for liquid waste disposal exist liquid waste shall be collected in bottles, kept in pails or trays designed to retain all their contents in the event of a breakage. Special containers which are provided with a suitable absorbent material for safe storage or licensed disposal are made available for liquid waste.
(4) All receptacles for radioactive wastes shall be clearly identified. In general it will be desirable to classify radioactive waste according to methods of storage or disposal and to provide separate containers for the various classes of waste. Depending upon the need of the installation, one or more of the following categories for classifying waste may be found desirable–
(a) gamma radiation levels (high, low);
(b) total activity (high, medium, low);
(c) half-life (long, short);
(d) combustible, non-combustible.
For convenient and positive identification, it may be desirable to use both colour, coding and wording.
(5) Shielded containers for radioactive waste shall be used when necessary in order to keep the radiation dose outside the container below the recommended level.
(6) Under the licence granted for accumulation and disposal of radioactive waste it is required that records shall be maintained of all radioactive wastes released to drainage systems or sewers, or disposed of by incineration or to the centre determined by the National Radiation Commission. These records shall contain information on the radionuclides, estimated radioactivity, volume and date of disposal. For this purpose it will be necessary to maintain a record of estimated quantities of radioactivity and radioisotopes deposited in the various receptacles at the work places, and for the receptacles to be labelled appropriately with this information.
(7) Radioactive waste shall be removed from working places to a suitably designed storage area with adequate shielding and security by a designated personnel under competent supervision.
54. Release of radioactive wastes to the environment
Release of radioactive wastes to the environment shall be carried out in accordance with the conditions established in the licence for the accumulation and disposal of radioactive wastes issued by the Commission in Schedule I.
55. Release of liquid radioactive waste to drains and sewers
The release of radioactive effluent to drains and sewers shall be carried out only in accordance with the conditions established in the licence for the accumulation and disposal of radioactive waste issued by the Commission in Schedule II.
56. Incineration of radioactive wastes
The incineration of radioactive wastes shall be carried out in a suitably designed incinerator approved by the Chief Radiation Protection Officer and under the conditions established in the licence for the accumulation and disposal of radioactive wastes issued by the Commission in Schedule I.
57. Radioactive waste storage
(1) All radioactive waste which cannot be immediately disposed of in conformity with the licence issued by the Commission shall be placed in a suitable storage.
(2) Storage of radioactive waste may be necessary to allow decay of short lived radionuclides to an activity level below the standard laid down for disposal via the non-active waste disposal routes, or by the radioactive waste disposal routes granted in the licence for accumulation and disposal of radioactive waste. Any radioactive waste that cannot be disposed of locally under this licence due to the activity levels of long-lived isotopes shall be transferred as soon as practicable to the place of storage.
PART X
RADIATION ACCIDENTS AND EMERGENCIES (reg 58)
58. Radiation accident
(1) A radiation accident is an unusual occurrence resulting from the loss of control over a radiation source which can indirectly involve hazards to life, health and property. A radiation accident may occur at any stage of an operation involving radiation sources.
(2) Radiation accidents will normally conform to one of the following broad general patterns–
(a) accidental external exposure to excessive amounts of radiation, for example when a person inadvertently remains close to a strong source or accidentally gets exposed to a beam of radiation;
(b) accidental spill or incident in a working place resulting in surface and air contamination of personnel; and in such cases the intake of radioactive materials into the body can be by inhalation, through open wounds resulting from the incident, or by direct absorption through the skin; and
(c) release of radioactive material into the environment as a result of an explosion, fire, mechanical shock or other incidents occurring on the licensed premises or in a public place when radioactive materials are being transported.
(3) The licensee has a responsibility to reduce as far as practicable any risks to his employees and other persons. He shall ensure that proper procedures are available so that if an accident shall occur, immediate steps are taken to protect the workers and other persons.
(4) In any incident, the first concern shall be protection of persons involved and the treatment of any serious injury. The second concern is to confine the contamination as far as possible to the area originally affected. Decontamination of personnel shall also take priority over any plan for decontamination of working areas, although immediate arrangements shall be made to restrict the spread of contamination.
(5) In every licensed premises for radiation sources local instructions shall be drawn up and made known to all workers and other persons within the establishment specifying–
(a) the person to be notified of an accident;
(b) immediate action to be taken; and
(c) the location of equipment for dealing with accidents.
(6) The designated Radiation Safety Officer shall provide instructions which shall be displayed at appropriate places in controlled radiation areas and other appropriate departments of the licensed premises for dealing with accidents or incidents involving radioactive materials.
(7) The following shall be kept in mind when drawing up instructions and plans for accident or incident situations–
(a) persons in the immediate vicinity shall be warned of the accident;
(b) all functioning laboratory apparatus shall be made safe and, normally, other laboratory services and ventilation except lighting, shall be switched off. All doors and windows shall be closed to restrict the spread of contamination by draughts. Access to the scene shall be restricted. However in those circumstances where radioactive gas or vapour, for example treated water vapour, is dispersed, the mechanical ventilation shall be left on and, according to discretion, the doors and windows shall be opened;
(c) access to and traffic through the affected areas shall be controlled and kept to the absolute minimum necessary for dealing with the incident;
(d) if it is necessary to evacuate all non-essential persons an attempt shall be made to ensure that contamination particularly on shoes or clothing, is not carried to other unaffected areas. If contaminated persons are evacuated they shall be monitored and measures to reduce surface contamination shall be taken as soon as possible;
(e) persons entering the affected area to carry out emergency procedure shall wear appropriate protective clothing;
(f) protective and, if possible, other outer clothing if contaminated with radioactive substances shall be removed and left in the affected area;
(g) decontamination of the contaminated persons shall be carried out as soon as possible; and
(h) appropriate radiation surveys shall be carried out.
(8) The following equipment shall be kept available for use in an emergency where appropriate–
(a) personnel protective equipment, including protective clothing, gloves, footwear and breathing apparatus;
(b) decontamination materials for the affected area including absorbent material for cleaning up spills;
(c) decontamination material for persons;
(d) cleaning equipment reserved for the purpose for cleaning in the active area;
(e) equipment for preventing entry into the affected area, including warning notices;
(f) equipment for the handling, temporary storage and disposal of contaminated articles;
(g) portable monitoring equipment including personnel monitoring devices;
(h) non-porous floor covering for example kraft paper (to be used only after any liquid spill has been cleared up);
(i) fire fighting equipment; and
(j) sundry items such as adhesive tape, labels, torch, notebook, pencils and simple first-aid equipment.
(9) After every accident the licensee and the person responsible for radiation safety shall carry out an investigation of the accident and a detailed written report shall be made on all findings, action taken, conclusions and recommendations for avoiding recurrence. This report shall be filed for future reference and a copy shall be sent to the Chief Radiation Protection Officer.
PART XI
NOTIFICATION OF ACCIDENTS (regs 59-62)
59. Notification of accidents
The licensee shall be responsible for immediately notifying the Chief Radiation Protection Officer by telephone or telegraph of any incident involving any source of radiation possessed by him and which may have caused or threatens to cause–
(a) a dose to the whole body an individual of 0.25 g-rays (25 rads) or more of radiation, a dose to the skin of the whole body of any individual of 1.5 g-rays (150 rads) or more of radiation, or a dose to the feet, ankles, hands, or forearms of 0.75 g-rays (75 rads) or more of radiation; or
(b) release of radioactive materials in concentrations which, if averaged over a period of twenty-four hours will exceed 5,000 times the derived concentration limits specified for such materials; or
(c) a loss of one working week or more of the operation of any facilities affected.
60. Twenty-four hours notification
Each licensee shall within twenty-four hours notify the Chief Radiation Protection Officer by telephone or telegraph of an accident involving sources of radiation possessed by him and which have caused or threaten to cause–
(a) a dose to the whole body of an individual of 0.05 g-rays (5 rads) or more of radiation, a dose to the skin of the whole body of an individual of 0.3 g-rays (30 rads) or more of radiation, or a dose to the feet, ankles, hands, or forearms of 0.75 g-rays (75 rads) or more of radiation; or
(b) release of radioactive materials in concentrations which, if averaged over a period of twenty-four hours will exceed five hundred times the derived concentration limits specified for such materials.
61. Reporting of over exposures and excessive levels of concentration
(1) In addition to any notification required under regulations 59 and 60, each licensee shall make a report in writing within thirty days to the Commission of–
(a) each overexposure of an individual to radiation in excess of applicable limits provided for in the Schedule II;
(b) each overexposure of an individual to radioactive material in excess of the applicable maximum concentration limits given in Schedule II;
(c) levels of radiation or concentrations of radioactive material in excess of any applicable limit in the licence;
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(d) any incident for which notification is required by regulations 59 and 60; and;
(e) level of radiation or concentrations of radioactive material (whether or not involving excessive exposure of any individual) in a restricted area in excess of ten times any applicable limit set forth in the part or in the licence. Each report required under this regulation shall describe the extent of each individual's exposure to radiation or to radioactive material including estimates of each individual's exposure as required by regulations 59 and 60, levels of radiation and concentrations of radioactive involved, the cause of exposure, levels of concentration, and corrective steps taken or planned to ensure against non-recurrence.
(2) Any report filed with the Commission pursuant to this regulation shall include for each individual overexposed, the identity card number, date of birth and an estimate of the individual's dose. The report shall be prepared so that this information is stated in a separate part of the report.
62. Notification and report to individuals
When a licensee is required pursuant to regulation 61 to report to the Chief Radiation Protection Officer about any exposure of an individual to radiation or radioactive materials, the licensee shall also notify the individual. Such notice shall be transmitted at a time not later than the transmittal time to the Chief Radiation Protection Officer.
PART XII
VACATING OF THE PREMISES (reg 63)
63. Vacating of the premises
Each specific licensee shall, in not less than thirty days before vacating or relinquishing possession or control of premises which may have been contaminated with radioactive material as a result of these activities, notify the Chief Radiation Protection Officer in writing of intent to vacate. When deemed necessary by the Commission, the owner shall decontaminate the premises in such a manner as the Commission may specify.
PART XIII
MISCELLANEOUS PROVISIONS (reg 64)
64. Compliance with regulations
(1) Each worker at risk of exposure to radiation must comply with all practices and regulations set out in this Code of Practice.
(2) The Radiation Safety Officer of each establishment using radiation shall be fully and solely responsible for the safe use of all radiation sources, isotopes and their safe disposal. He will also be responsible for instructing workers in the safe use of ionising radiation and must ensure that proper working techniques and safety precautions are observed.
(3) The Chief Radiation Protection Officer from the National Radiation Commission shall be authorised to inspect installations using radiation at any time and shall be given full facility and assistance by the head of the establishment where radiation is used and by the Radiation Protection Officer at that place.
(4) Radiation workers who will fail to use proper methods and to take adequate precautions shall be responsible for the consequences. The Commission's disciplinary Committee is authorised to make appropriate penalty to such persons.
(5) Conditions of employment and position of radiation workers shall be such as to attract and retain conscientious, responsible and well-trained staff. It is recommended to the employer that he gives incentives such as increased salary, special radiation allowance, reduced house rent, extra holidays and special diet, etc.
FIRST SCHEDULE
APPLICATION FORMS, LICENCES, REGISTRATION CERTIFICATES AND REGISTERS UNITED REPUBLIC OF TANZANIA
FORM NRC 1
APPLICATION FOR LICENCE AND REGISTRATION FOR THE USE OF RADIATION DEVICE
THE PROTECTION FROM RADIATION ACT (CAP. 188)
PART III (Sections 15 and 18)
Ref: | ||
For Official Use only |
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1. | Name of applicant ................................................................................................ |
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Tel No. ................................................................................................................ |
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Address .............................................................................................................. |
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2. | Name and address of owner where the radiation devices will be used, stored or installed |
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Premises Licence/Registration No. ........................................................................ |
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3. | Name and address of person responsible for radiation safety .................................... |
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Title ...................................... Reg./Licence No. 1 .................................................. |
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4. | List of names of licensed users Reg./Licence No. 2 .................................................. |
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........................................................... | ........................................................... |
PART "A"
X-RAY EQUIPMENT
(A separate form must be filled for each x-ray equipment)
5. | Identification: | Name of manufacturer ............................................ |
Model ................................................................... |
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Equipment control panel type .................................. |
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Serial No. .............................................................. |
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Tube head type ...................................................... |
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Serial No. .............................................................. |
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Tube insert type ..................................................... |
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Serial No. .............................................................. |
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6. | Type of installation: | 3 (a) Fixed/mobile; |
4 (b) combine/Radiographic/Fluoroscopic photofluorographic/cine fluorography/dental, other. |
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7. | Rectification: | Specify ................................................................ |
Single phase, self rectified/half wave rectified/full |
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5 Three phase: six pulse/twelve pulse/constant potential, capacitors storage. |
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8. | For Combine Radiographic/ fluorographic: | 6 Indicate whether with bulky radiography/ Serial radiography/tomography/fluorescent screen/image intensifier with sport camera for 70mm/100mm of optical viewer or television/cine camera for 16mm/35mm continuous operation/pulsed operation. |
(specify) max. |
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frame speed .......................................................... |
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frames/sec. .......................................................... |
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9. | Tube Rating: | (a) For capacitor-discharged equipment |
Peak tube voltage ............................................. |
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Max. quality charge ........................................... |
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Coulombs or condenser capacitor ....................... |
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(b) For Pulsed Equipment |
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Peak Tube voltage ............................... kVp Max |
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No. of x-ray pulses ........................................... |
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(c) For Other Equipment |
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Peak tube voltage ........................................ kVp |
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Max. tube current .......................................... ma |
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Max. Exposure time .................................... sec. |
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or Max. tube current and exposure time ................. |
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10. | Filtration: | Inherent ..................................................... mm AL. |
equivalent added ......................................... mm AL. |
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equivalent AL = Aluminium Total .................. mm AL. |
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11. | Time: | 7 (a) Built in monitoring system/filter safety switch. |
8 (b) Automatic exposure control-photo-timer ionisation type. |
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12. | Tube insert: | Stationary anode/rotating anode .............................. |
9 Air cooled/oil cooled grid controlled/non-grid controlled. |
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Fine focus ............................................................. |
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Broad focus ........................................................... |
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Head storage capacity ............................................ |
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Cooling rate ........................................................... |
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13. | Stabilisation: | 10 Mains voltage stabilisation/the voltage stabilisation/tube current stabilisation. |
Specify % fluctuation in output. |
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14. | Collimation: | 11 Cones/single-leaf/multi-leaf/applicators/ light beam. |
15. | Directions in which exposure can be made: | 12 One direction/two directions/multi-directional (indicate directions in the drawing of premises). |
16. | Intended Use: | Describe the intended use of the radiation device |
17. | Cost of devices: | ............................................................................. |
PART "B"
ACCELERATOR OR NEUTRON GENERATOR OR THERAPY MACHINE
(A separate form must be filled for each accelerator or generator or therapy machine.)
18. | Identification: | 13 Electron accelerator/heavy participle accelerator/ neutron generator/therapy unit. |
Type of machine .................................................... |
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Name of Manufacturer ............................................ |
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Model control panel Sr. No. .................................... |
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Approx date of manufacture .................................... |
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Country of manufacture .......................................... |
19. | Operational Factors: | To be completed for all accelerators and neutron generators. |
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Primary particle accelerated | Energy range | Peak beam | Average current | Target material | Target thickness |
(a) .................................................................................................................. |
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(b) .................................................................................................................. |
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(c) .................................................................................................................. |
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(d) ................................................................................................................. |
20. | To be completed for therapy machines only. |
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Energy values of primary beam used for Radiotherapy | Related given dose rates of 10cm x 10cm field size | Secondary Radiation produced | Energy value of Secondary beam used for Radiotherapy | Given dose of 10cm x 10cm field |
(a) .................................................................................................................. |
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(b) .................................................................................................................. |
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(c) .................................................................................................................. |
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(d) .................................................................................................................. |
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21. | No of beam parts ................................................................................................... |
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22. | Type of collimation ................................................................................................ |
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23. | No. of afterload therapy units in your possession ..................................................... |
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24. | Give the total cost of the devices in this class T.Shs. ............................................... |
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25. | Intended use ........................................................................................................ |
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26. | Declaration: I .............................................................................................. hereby |
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Date ......................................... Signature of Applicant: ........................................ |
LICENCE AND REGISTRATION CERTIFICATE AUTHORISING
THE HOLDER TO POSSESS OR USE RADIATION DEVICES
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 15 and 18)
National Radiation Commission | Licence No. ........................................ |
14 Dr./Mr./Mrs./Miss. ........................................................................................................... Title: ............................................................................................................................... Box: ................................ Town: ............................................. Street: ............................ District: ............................................................ Region: .................................................. is hereby registered and authorised by the National Radiation Commission to possess or use radiation devices in accordance with sections 15 and 18 of the Act and subject to the conditions imposed hereunder. |
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.......................................................... |
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Conditions of Licence and Registration Authority: |
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1. This certificate is valid for the duration of the holder's service in the government or exempted institutions from the above date. |
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2. The holder is authorised to specific nature of possession or usage of radioactive material or radiation device ........................................................................................................... |
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3. Others ....................................................................................................................... |
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Date ............................................. Signature of Holder .................................................... |
FORM NRC 2
APPLICATION FORM FOR A LICENCE TO POSSESS OR USE RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Part III (Section 15))
Ref: | For Official Use only |
1. Name of person responsible for Radiation Safety at the area of use or installation ................................................................................................................................... |
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2. Registration Licence No. ............................................................................................... |
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3. Name and address of Unit/Dept. where radioactive materials will be used: ......................... |
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Town ......................................................... Street ....................................................... Building ..................................................... Room ....................................................... Premises Licence/Registration No. ................................................................................ |
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4. List names of individual users: .......................................................... | Registration or Licence No. .......................................................... |
5. Radioactive materials: Give details of all radioactive materials that you will possess at any one time (use separate sheet where necessary). |
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Element mass number | Chemical or physical state | Number of sources | Activity | Model No. and name of manufacturer | Sale price in T.Shs. |
....................................................................................................................................... |
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6. Describe the purpose for which Radioactive materials will be used (if by product material is in the form of a sealed source include the make and mode of the storage container and/or device in which the source will be stored and/or used). |
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7. Radiation Protection: Describe the general radiation protection measures that will be taken. Also submit leak testing procedures where applicable, arrangements for performing initial radiation survey, service maintenance and repair for source equipment. |
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8. Waste Disposal: Submit detailed description of method which will be used for disposing of radioactive wastes and estimates of the type and amount of activity involved. |
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9. Declaration: I .................................................... certify that all information contained in this application including any supplements attached thereto is true and correct to the best of my knowledge. |
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Date: .................................. | Signature of Applicant ................................ |
LICENCE AUTHORISING THE BEARER TO POSSESS OR USE RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 15 and 18)
National Radiation Commission | Licence No. ........................................ |
1 Dr./Mr./Mrs./Miss: ......................................................................................................... |
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Title: ............................................................................................................................... |
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Address: ......................................................................................................................... |
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Township: ....................................................... Street: ..................................................... |
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District: .......................................................... Region: ..................................................... |
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is hereby licensed by the National Radiation Commission to possess or use radioactive materials in accordance with sections 15 and 18 of the Act and subject to the conditions imposed hereunder. |
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................................................................ |
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Conditions of licence: | |
1. This licence is valid from ......................................... to ........................................ |
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2. The licensee is authorised to possess or use radioactive materials listed on the application form as appears in the register. Others: ....................................................................................................................... |
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Date: ................................... | Signature of Holder ..................................... |
FORM NRC 3
APPLICATION FOR DISPOSAL OF RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 24 and 25)
Ref: | |
National Radiation Commission | For Official Use only |
1. Name and address of applicant ..................................................................................... |
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2. Title ........................................................................................................................... |
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3. Licence or Registration Certificate No: .......................................................................... |
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4. Describe the intended method of disposal (e.g. river, sewage, solid waste tipping, burial, incineration, restricted storage or other methods) |
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5. What Radiation Protection measures will you take to ensure that disposal methods do not alter existing safety procedures and regulations? |
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6. To what extent will the disposal method affect the maximum permissible concentration of the disposal route? ...................................................................................................... |
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7. Identify the Radiation sources to be disposed of: (a) Name of Manufacturer................................................ Model ............................... (b) Control Panel Type ............................................................................................. (c) Serial No. .......................................................................................................... |
Element & Mass Rad. Material | Chemical / Physical State | Activity | Name of Manuf./ Suppl. | Model No. |
........................................................................................................................................ |
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(d) Other (specify) ................................................................................................... I ........................................................................................................................ |
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Signature: ......................................................... Full names: ....................................................... Title: ................................................................. |
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Note: A fee of Shs. 500/- which may be reviewed from time to time by the Minister on the advice of the National Radiation Commission, is charged on this application to all institutions and persons unless the disposal of radioactive materials is covered by an exemption order. Exempted owners must possess a disposal licence which is free of charge. |
LICENCE AUTHORISING DISPOSAL OF RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 7, 24 and 25)
National Radiation Commission | Licence No. .......................................... |
1 Dr./Mr./Mrs./Miss: ........................................................................................................... |
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of ................................................................................................................................... |
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licensed or registered under .............................................................................................. |
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............................................................ |
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Conditions of Licence: | |
1. This licence is valid from .............................................................................................. |
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2. The method of disposal is through sewage/incineration/burial or confined storage. |
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3. The activity authorised for disposal is ............................................................................ |
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4. Others ....................................................................................................................... |
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5. Date: ......................................................................................................................... |
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Signature of Holder ................................................................ |
FORM NRC 4
APPLICATION FOR RADIATION PREMISES LICENCE
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 7, 15 and 40)
National Radiation Commission | For Official Use only |
1. Name of owner ............................................................................................................ |
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Tel No. .......................................................... |
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2. Location of Facility: |
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Name of Unit/Dept. ...................................................................................................... |
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Place: Land Reg. No./ Vehicle Reg. No. ........................................................................ |
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Sub-Location/Town ...................................................................................................... |
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Location/Street ........................................................................................................... |
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Division ...................................................................................................................... |
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District ....................................................................................................................... |
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Building ...................................................................................................................... |
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Room No ............................................................................ Floor ............................... |
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3. Name of person responsible for radiation safety: ............................................................. ................................................................................. Tel No. ...................................... |
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Licence Reg. No. ......................................................................................................... |
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4. Is this a New/Renewable application? ............................................................................ |
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5. Type of facility: Medical/Industrial/School/Research/other (specify) ................................... |
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6. Classification of facility: Government/Local Government Authority/Missionary/Statutory body/Public Co. Ltd/Private Hospital/other (specify) ........................................................ |
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7. Type of installation: Enclosed installation/open installation– |
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(a) Enclosed installation: With the aid of diagram of plan to be attached, describe the appropriate facility or room with special reference to– |
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(i) Construction materials ................................................................................ |
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(ii) Interlock systems ....................................................................................... |
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(iii) Warning signal installed .............................................................................. |
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(iv) Equipment lay-out....................................................................................... |
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(v) Radiation shields ........................................................................................ |
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(vi) Fume hoods ............................................................................................... |
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(vii) Remote handling equipment ......................................................................... |
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(viii) Any other protective measures/and devices ................................................... |
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Note: Indicate in diagram or plan the directions in which exposure is possible: |
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(b) Open installation: | |
(i) State why an enclosed installation is not likely to be practicable: .................... |
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(ii) Indicate the distance from the radiation source within which unauthorised persons are not allowed to enter: ............................................................................... ................................................................................................................. |
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(iii) Indicate positive measures to be taken to maintain this degree of isolation: |
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(iv) How will you ensure that radiation workers involved will be adequately protected? ................................................................................................................. |
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8. Enclose architectural drawing of the premises. |
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9. Declaration by Owner: |
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Date ................................................. Signature of Applicant: ........................................... |
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Note: A fee of T. Shs. 5,000/- which may be reviewed from time to time by the Minister on the advice of the National Radiation Commission is payable annually for a licence. |
RADIATION PREMISES LICENCE
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 7, 15 and 40)
National Radiation Commission, | Licence No. ........................................... |
Name of premises: .......................................................................................................... |
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Owner of premises (Name): .............................................................................................. |
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Located on: ........................................................... Township: ......................................... |
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Street: ............................................................ Division: .................................................. |
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District: ................................................................. Region: ............................................. |
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Address: .......................................................................................................................... |
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is licensed by the National Radiation Commission as premises for housing, storing and installation of radiation devices or radioactive materials in accordance with section 15 of the Act subject to the conditions set hereunder. |
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........................................................... |
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Conditions of licence: | |
1. This licence is valid from ............................................. to ............................................ |
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2. The facility is licensed for housing, storing and installation of (state specific type of device or material) .................................................................................................................... |
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3. The owner named above shall put to force Part IV and V of the Act before the device or material has been put to use. |
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Date ........................................... Signature of Holder .................................................. |
FORM NRC 5
APPLICATION FOR MODIFICATION OF RADIATION PREMISES MATERIALS OR DEVICES
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 7 and 17)
Ref: | |
National Radiation Commission, | For Official Use Only, |
1. Name and address of applicant: ................................................................................... |
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2. Title ........................................................................................................................... |
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3. Licence or Registration Certificate No. .......................................................................... |
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4. Describe nature and extent of modification (provide technical drawings of the modification if it is for a facility or a device): |
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5. Who will carry out the modifications (give licence number or authority reference)? ................................................................................................................................... |
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6. What radiation protection measures have you taken to ensure that modifications do not |
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7. To what extent will the modification affect the workload of the equipment or operation within the facility? ................................................................................................................. |
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8. Identify the device to be modified: |
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(a) Name of Manufacturer ........................................... Model .................................. |
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(b) Control Panel Type ...................................... Sr. No............................................ |
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(c) Tube-insert type ......................................... Sr. No............................................ |
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(d) Type of Therapy Unit ......................................................................................... |
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(e) Others (specify)................................................................................................. |
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9. I ................................................................................................................................. |
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Signature: .................................................................... Full names: ........................................... Title ............... |
LICENCE AUTHORISING MODIFICATION OF LICENSED RADIATION PREMISES, MATERIALS OR DEVICES
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 7 and 17)
National Radiation Commission | Licence No. ........................................... |
1 Dr./Mr./Mrs./Miss: ........................................................................................................... |
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of ................................................................................................................................... |
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or Registration No. ............................................................................................................ |
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is hereby licensed by the National Radiation Commission to modify his radiation premises, materials or device in accordance with Sector II and subject to the conditions imposed hereunder. |
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............................................................ |
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Conditions of licence: |
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1. This licence is valid from .............................................. to ............................................ |
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2. Specific area of article to be modified ............................................................................ |
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3. For modification of devices only registered installation, service or maintenance personnel may make such modification. |
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Date: ............................................. Signature of Holder ............................................... |
FORM NRC 6
APPLICATION FOR LICENCE TO SELL, LEASE OR DEAL WITH RADIATION DEVICES OR RADIOACTIVE MATERIAL
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 15, 18 and 40)
Ref: | |
National Radiation Commission, | For Official Use Only, |
1. Name and address of the seller .................................................................................... |
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2. Trade Licence No. ....................................................................................................... |
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3. Type of radiation devices or radioactive material you intend to sell, lease, loan or deal with: .................................................................................................................................. |
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4. For what purpose will the radiation devices/materials be used (e.g. Medical, Scientific, Educational or Commercial)? |
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5. Is the equipment new or old?........................................................................................ |
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6. Name(s) of authorised installation, service or maintenance Engineers/Technologists indicating their registration and licence numbers: ........................................................... |
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7. Is the application for a co-operation or Limited Company business?.................................. |
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8. Declaration: I .............................................................................................................. |
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Date: .......................................... Signature of Applicant .............................................. |
A LICENCE TO SELL, LEASE OR DEAL WITH RADIATION DEVICES OR RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Sections 15 and 40)
National Radiation Commission, | Licence No. ...................................... |
1 Dr/Mr/Mrs/Miss: ............................................................................................................. (Full Name in BLOCK CAPITAL LETTERS) |
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Location: ......................................................................................................................... |
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Classification: .................................................................................................................. |
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Is hereby registered and licensed by the National Radiation Commission pursuant to sections 15 and 40 of the Act to sell radiation devices/radioactive materials at the above location and subject to the conditions hereunder. |
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............................................................... |
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Conditions of the Licence: | |
1. The licence is valid from ............................................ to............................................. |
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2. The licensee shall comply with the provisions of section 16(2) of the Act. |
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3. The licensee shall keep a register of all buyers together with revenue payment receipt at the rate determined by the committee from time to time. |
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4. Others (specify) .......................................................................................................... |
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Date: .............................................. Signature of Holder .............................................. |
FORM NRC 7
IMPORT/EXPORT LICENCE APPLICATION FOR RADIATION DEVICES OR RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Section 14)
Ref: | |
National Radiation Commission, | For Official Use Only |
1. Name and address of applicant .................................................................................... |
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2. Purpose of which the device or material will be used (Sale, Medical, Agriculture, Scientific Research, Industrial, or others - specify) ........................................................................ |
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3. Valid licence or registration certificate number of the Consignee (purchaser): .................................................................................................................................. |
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4. Give a list of all the devices or radioactive materials you intend to 1 import/export: ................................................................................................................................... |
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5. Give details of storage and transportation compliance with the regulations on safe handling, storage and transport of radioactive materials (enclose additional information in separate sheet if need be): ........................................................................................... |
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6. Give the estimated sale price of the total items: .............................................................. |
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7. Declaration: I .............................................................................................................. |
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Date: ....................................... Signature of Applicant ................................................. |
LICENCE AUTHORISING THE BEARER TO IMPORT/EXPORT RADIATION DEVICES OR RADIOACTIVE MATERIALS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Section 14)
National Radiation Commission, | Licence No. .......................................... |
2 Dr./Mr./Mrs./Miss: ......................................................................................................... |
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Title: .............................................................................................................................. |
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Address: ........................................................................................................................ |
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Township: ........................................................... Street: ................................................ |
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District: ............................................................. Region: ................................................ |
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is hereby licensed by the National Radiation Commission to 3 import/export radiation devices or radioactive materials is accordance with section 14 of the Act and subject to the conditions imposed hereunder. |
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........................................................... |
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Conditions of Licence: | |
1. This licence is valid from ............................................ to ........................................... |
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2. The licensee is authorised to import or export radiation devices or radioactive materials listed in the application form. |
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3. Others (specify) ......................................................................................................... |
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Date .............................................. Signature of Holder ............................................... |
FORM NRC 8
APPLICATION FOR A LICENCE TO ADMINISTER IONISING RADIATION TO PERSONS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Section 19)
Ref: | |
National Radiation Commission, | For Official Use Only |
1. Surname (BLOCK LETTERS) ...................................................................................... |
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2. Other Names (BLOCK LETTERS) ................................................................................ |
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3. Address ..................................................................................................................... |
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4. Place and Date of Birth ............................................................................................... |
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5. Nationality .................................................................................................................. |
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6. Degree, Diploma or certificate held (give name of College and date qualified) .................... (Legible certified true photocopies should be supplied) |
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7. Particulars of experience (e.g. posts held, type of work in which the applicant has been engaged, countries in which the applicant has worked) |
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8. Testimonials covering the period(s) of experience............................................................ (Photocopies should be supplied for record purposes) |
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Signature of Applicant: ................................................................................................ |
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Date .................................................... |
LICENCE TO ADMINISTER IONISING RADIATION TO PERSONS
UNITED REPUBLIC OF TANZANIA
THE PROTECTION FROM RADIATION ACT (CAP. 188)
(Section 19)
National Radiation Commission, | Licence No. .......................................... |
1 Dr./Mr./Mrs./Miss: .......................................................................................................... (Full names BLOCK LETTERS) |
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of ................................................................................................................................... |
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Qualification: .................................................................................................................... |
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is hereby licensed by the National Radiation Commission to administer ionising radiation to persons with 2 X-rays/isotopes/electron generators for diagnosis/therapeutic work at ...................................................................................................................................... |
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Dated this ......................... day of ......................... 20........ |
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............................................................ |
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Conditions of Licence: | |
1. This licence is valid for a period ............................................ from ................................. |
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2. The licensee is authorised to administer ionising radiation only at the institution mentioned. |
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3. This licence 3 does/does not entitle licensee to engage in private practice. |
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4. Signature of the Holder ............................................................................................... |
SECOND SCHEDULE
THE SYSTEM OF DOSE LIMITATION
1. Introduction
The detrimental effects against which protection is required are known as somatic and hereditary. Radiation effects are called "somatic" if they become manifest in the exposed individual himself, and "hereditary" if they affect his descendants.
"Stochastic" effects are those for which the probability of an effect occurring, rather than its severity, is regarded as a function of dose without threshold.
"Non-stochastic" effects are those for which the severity of the effect varies with the dose and for which a threshold may therefore occur. At the dose range involved in radiation protection, hereditary effects are regarded as being stochastic. Some somatic effects are stochastic; of these, carcinogenesis is considered to be the chief somatic risk of irradiation at low doses and therefore the main problem in radiation protection.
The aim of radiation protection should be to prevent detrimental non-stochastic effects and to limit the probability of stochastic effects to levels deemed to be acceptable.
The prevention of non-stochastic effects would be achieved by setting dose equivalent limits at sufficiently low values so that no threshold dose would be reached, even following exposure for the whole of a lifetime or for the total period of working life.
The limitation of stochastic effects is achieved by keeping all justifiable exposure as low as is reasonably achievable, subject always to the boundary condition that the appropriate dose equivalent limits shall not be exceeded. For the above reasons, the International Commission on Radiological Protection (I.C.R.P.) recommended a system of dose limitation, the main features of which are as follows–
(a) no practice shall be adopted unless it introduction produces a positive net benefit;
(b) all exposure shall be kept as low as reasonably achievable economic and social factors being taken into account.
2. Radiological consideration and dose limits
The relationship between the dose received by an individual and any particular biological effect induced by irradiation is a complex matter. I.C.R.P. recommended that regarding stochastic effects, there is within the range of exposure conditions usually encountered in radiation work, a linear relationship without threshold between dose and the probability of an effect.
For the purposes of radiation protection it is necessary to specify a number of organs and tissues that have to be considered because of their susceptible to radiation damage. For protection purpose sufficient accuracy is obtained by using a single dose equivalent limit for each organ or tissue for all workers regardless of age or sex. These limits are based upon the average risk levels.
The system of limitation includes justification of the practice, optimisation of radiation protection and recommendation of annual dose equivalent limits. The primary limit quantities are–
The effective dose equivalent H(E)–
For uniform as well as non-uniform irradiation of the whole body, in order to assess the risk of those effects of radiation exposure for all those organs for which proportionality between dose equivalent and probability of effect is assumed (stochastic effects); H(E) is defined as the sum of the risk weighted mean dose equivalents in relevant body tissues, i.e.
Where H(E) is the sum of the weighted organ dose equivalent called the effective dose equivalent.
W(T) is a weighting factor representing the fraction of risk resulting from tissue T when the whole body is irradiated uniformly, and H(T) is the annual dose equivalent in tissue T. The values of W(T) recommended by the I.C.R.P are–
Gonads ............................................. | 0.25 |
Breast................................................ | 0.15 |
Red bone marrow................................ | 0.12 |
Lung................................................... | 0.12 |
Thyroid............................................... | 0.03 |
Bone surface....................................... | 0.03 |
Remainder......................................... | 0.30 |
Regarding the remainder, the I.C.R.P. recommends that a value of W(T) = 0.06 be applied to each of the five organs or tissues receiving the highest dose equivalent, and that the exposure of all the other remaining tissues may be neglected (stomach, small intestine, upper intestine and lower large intestine are to be treated as four different organs). The skin, lens of the eye, hands, forearms, feet and ankles are not considered in computing the effective dose equivalent.
The dose equivalent H(T):
In specific tissues or organs (T) i.e. the skin of the whole body, the lens of the eye and the extremities (including their skin) in order to assess the risk of those effects of radiation for which a threshold may exist (non-stochastic effects), H(T) is defined as the mean dose equivalent in the relevant tissue but in the case of skin, it is the average dose equivalent over a defined area.
In order to specify acceptable limits for human exposures the I.C.R.P. introduced limits for primary dose quantities in specified tissues. The dose equivalent limits for workers are as follows–
(i) to prevent the occupance to non-stochastic effects a limit of 0.5Sv (50rem) in a year applies to all tissues except the lens of the eye, for which the recommended annual limit is .15Sv (15rem). These values apply irrespective of whether tissues are exposed singly or in combination with other tissues, and are intended to constrain exposure that fulfil the limitation for stochastic effects given below;
(ii) for stochastic effects, the quantity which is limited is the effective dose equivalent H(E) the annual limit being 50mSv (50rem).
The dose equivalent limits are not intended to be designing or planning objectives but are the lower boundary of a forbidden region of values. Values above the limits are specifically not permitted, but values below the limits are not automatically permitted. In this sense, the limits are the constraint for the optimisation procedures.
The effective dose equivalent H(E) is essentially unmeasurable and, as a result is must be estimated on the basis of dose equivalents determined at appropriate locations in suitable receptors.
The I.C.R.P. recommended two concepts for purposes of individual monitoring. The first of these concepts, the individual dose equivalent penetrating. Hp(d) is appropriate for deep organs which will be irradiated by strongly penetrating radiation. Hs(d) is suitable for shallow organs which will be irradiated by both weakly and strongly penetrating radiation. The recommended depth d for Hp is 10mm and Hp(d) may be written as Hp(10). The recommended depth d for Hs is 0.07mm and Hs(d) may be written as Hs(0.07); Hp(10) at a given location on the anterior portion of the trunk can be related to the H(E) received by the trunk for radiation incident from anteriorly to laterally on the body, (annual dose limit 50 mSv). Also, a dosimeter indicating Hs(07) will usually provide an adequate estimate of the dose equivalent to the exposed skin (the annual limit for any small area of skin is 500 mSv). In most exposure conditions, the dose equivalent limit for the lens of the eye will not be exceeded when the limits for the effective dose equivalent and the dose equivalent to the skin are not exceeded.
Internal exposure resulting from the intake of radionuclides can be based on annual limits of intake (ALI) which, for some of the radionuclides are mentioned further.
The dose equivalent for the prevention of non-stochastic effects is the sum of any dose equivalent in a particular organ or tissue from external exposure during a year and the committed dose equivalent from any intake of radionuclides to that organ or tissue during that year.
The dose equivalent for the control of stochastic effects is the sum of any effective dose equivalent for external exposure during a year and the committed effective dose equivalent from any intake of radionuclides during that year.
Summation of internal and external exposure is performed by reference of such exposure to the two secondary limits for external exposure, i.e. the annual limits for the 10mm and the 0.07mm dose equivalents and the secondary limit for the intake of radionuclides, i.e. The Annual Limit of Intake (ALI);
2. Where Hp(10) is the annual dose equivalent recorded for body exposure of deep lying organs, H(0.07) is the annual dose equivalent recorded for skin exposure, H(E,L) is the annual effective dose equivalent for workers (50mSv), H(sk,L) is the annual dose equivalent limit for the individual organs and tissues for workers (500 mSv), Ij is the annual intake of radionuclide j and Ij, L is the ALI for radionuclide j. Compliance with primary limits is achieved if neither of these expressions exceeds one unit.
THE IAEA PUBLICATION SAFETY SERIES No. 9
"Basic Safety Standards for radiation protection" 1982 Edition included in Annex III are the Annual Limits on Intake (ALIs) and derived air concentrations (DACs) of all radionuclides for occupational exposure. This publication is available in the National Radiation Commission Library and the Chief Radiation Protection Officer (CRPO) will use these recommendations before the licence is given for application of open radionuclide sources.
THIRD SCHEDULE
TYPES OF RADIATION AND PRIMARY DOSE QUANTITIES
1. Alpha Particles
Alpha particles are helium nuclei emitted mainly by heavy radionuclides such as polonium, radium, thorium, uranium, etc. They have well defined and characteristic energies and as they are doubly charged and move relatively slowly, they are densely ionising and thus, in spite of their high energies, their penetrative power or range is extremely limited. In fact, alpha particles of energies up to 7.5 MeV are incapable of penetrating the protective layer of skin on most parts of the body. Their range in air is only a few centimetres. Thus, shielding against this type of radiation presents no problem, but hazard from ingestion or inhalation into the body of alpha radioactive materials is great.
2. Beta Particles
Beta particles are high-energy electrons created and emitted by certain radionuclides. Beta particles are emitted in a continuous energy spectrum and hence tables of beta energies always list the maximum energy of emission which is characteristic for each radionuclide. Beta particles loose energy mainly through ionisation, but may also loose energy by the production of bremsstrahlung (Braking radiation). For a given energy, beta particles have a much greater range than alpha particles. In addition because of their small mass, beta particles undergo frequent scattering with little loss of energy, a process analogous to reflection form surfaces, and referred to as backscattering.
The extent of backscattering increases with the atomic number of the surface material from which it is reflected. Thus in the design of shielding for pure beta emitters particular attention should be paid to the possible production of bremsstrahlung.
3. Protons
Protons are hydrogen nuclei and are therefore positively charged. Proton beams are produced in accelerators of different types and may have energies of several hundreds of MeV. Protons are also emitted in the interactions of fast neutrons with hydrogen atoms.
4. Neutrons
The neutron is an uncharged particle having a mass slightly higher than that of a proton. Neutrons are generally classified according to their energies under four broad categories.
(a) Thermal neutrons–
are those which are in thermal equilibrium with the surrounding matter. These neutrons will have most probable velocity of 2.3 x 10
(b) Intermediate neutrons–
are those falling in the energy range of 0.5 cV to KeV. Neutrons having energies less that 100cV are also referred to as slow neutrons.
(c) Fast neutrons–
have energies between 10 KeV and 10 MeV.
(d) Relativistic neutrons–
have energies greater than 10 MeV. The interaction of neutrons with matter is quite different from that of either charged particles or gamma rays. Depending on their energy neutrons, interact with matter by various processes–
(a) Elastic scattering.
(b) Inelastic scattering.
(c) Capture.
(d) Particle emission.
(e) Fission.
Essentially the absorption of neutrons occurs in two stages: Fast neutrons are slowed down by elastic and inelastic scattering processes with nuclei, particularly light nuclei such as carbon and hydrogen. The slowed-down neutrons are then captured. The capture cross-section for low-energy neutrons is high for most elements.
5. X- and Gamma rays
X- and gamma rays are electro-magnetic radiation of very short wave lengths. There is no difference between them except in their origin. Gamma rays are emitted with discrete energies characteristic of the nuclei. X-ray emission is of two types: characteristic radiation (discrete energies) and bremsstrahlung (continuous spectrum energies).
There are a number of ways in which electro-magnetic radiation may interact with matter producing electrons and protons with lower energies (photo-effect and co-emption effect).
PRIMARY DOSE QUANTITIES AND UNITS:
1. Exposure (X)
The exposure X, is the quotient of dQ divided by dm where the value of dQ is the absolute value of the total charge of the ions of one sign produced in air when all the electrons and/or positrons liberated by photons in air of mass dm are completely stopped in air:
X = dQ/dm
Unit: Coulomb per kilogram (C/kg)
In practice, the former special unit roentgen (R) is still sometimes used.
1 R = 2.58 x 10>
2. Absorbed Dose (D)
As defined by I.C.R.U., the absorbed dose (D) is the quotient of dE divided by dm, where dE = 0.01g-ray (Gy); 1Gy = 1J/kg. (The old unit of absorbed dose is the rad:
1 rad = 10
The absorbed dose (D) is the most important physical quantity employed to specify the irradiation of biological material. However, the relation between a given biological radiation effect and absorbed dose will change when the type of radiation or other conditions are varied.
3. Kerma (K)
Kerma is an abbreviation for kinetic energy released in material and is defined by the quotient:
K = dE(tr)/dm
Where dE(tr) is the sum of the initial kinetic energies of all the charged ionising particles liberated by the uncharged ionising particles in a material of mass dm. The quantity dE(tr) includes the kinetic energy expended by these charged particles in collisions and the energy radiated as bremsstrahlung and also the energies of any secondary charged particles such as the delta radiations produced within the volume element. In a situation where charged particle equilibrium exists at the point of interest and the bremstrahlung losses are neglible, kerma is approximately equal to the absorbed dose at the point. Kerma is slightly less than the absorbed dose when there is a transient charged particle equilibrium in beams of moderately high-energy X-rays or gamma radiation or neutrons.
4. Dose Equivalent (H)
All ionising radiations can produce the same kind of biological effect. However, certain radiations are more effective than others per unit absorbed dose. This means that a smaller absorbed dose of such radiations is required to produce a given degree of effect because the biological effect appears to depend upon the spatial distribution of the energy released along the track of the ionising particle. Generally the effect of radiation on a cell structure increases with increasing energy loss per unit path length (linear energy transfer LET), although certain single-hit effects such as the inactivation of bacterial and viruses, become less efficient per unit energy absorbed as the LET increases. The RBE (relative biological effectiveness) is defined as follows–
RBE = Absorbed dose due to 250kV X-rays causing a specific effect, divided by the Absorbed dose due to other radiation causing the same effect, e.g. Dx-rays/DNeutrons = RBE. The use of the term RBE both in radiobiology and Radiation protection presented certain problems, so the International Commission of Radiation Units and measurements (ICRU), recommended that the term RBE be used in radiobiology only. For radiological protection purposes a separate term, the quality factor (Q), is used which depends on the linear energy transfer to charged particles. The relationship between the linear energy-transfer coefficient (L(oo)) and the quality factor (Q) is the following.
L(oo) in water | Quality factor |
(keV. per micrometer) | Q |
3.5 or less | 1 X-and Gamma rays |
7 | 2 Thermal neutrons |
23 | 5 Epithermal neutrons |
53 | 10 Neutrons and protons, etc. |
175 and above | 20 Alpha and other multiply charged particles. |
The absorbed dose (D) can be weighted by a number of dimensionless factors (N) in such a way that the resultant quantity correlates with the magnitude or the probability of a biological effect. The dose equivalent (H) is defined by the equation:
H = DQN
At present, N is taken to be equal to 1 for irradiation by external sources. The dose equivalent has the same dimensions as the absorbed dose but it is not the same quantity. The special unit of H is the sievert (Sv); 1Sv = 1J/kg. (the old unit of dose equivalent is the rem):
1rem = 10>
The relationship between Q and L recommended for radiation protection is given in the above mentioned table.
5. Dose Equivalent in Specified Tissues or Organs (H(T))
The dose equivalent H(T) in specified tissues or organs is the mean dose equivalent in the relevant tissue or organ. In the case of skin it is the average dose equivalent over a defined area.
With respect to the I.C.R.P. system of dose limitation, the specified tissues are the skin, the lens, the eye and the extremities.
6. Effective Dose Equivalent (H(E))
This unit is defined in Schedule II Part X.
(Section 40(1))
[20th February, 1998]
G.N. No. 63 of 1998
1. Title
These Regulations may be cited as the Protection from Radiation (Control of Radiation Contaminated Foodstuffs) Regulations and shall be read as one with the Food (Control of Quality) Regulations *.
2. Interpretation
In these Regulations, unless the context requires otherwise–
"Act" means the Protection from Radiation Act *;
"certificate" means a written authorization issued by the Commission after a radioactivity analysis has been conducted on any commodity listed in the First Schedule;
"Commissioner" means the National Radiation Commission established by section 5 of the Act;
"exporter" means any person undertaking a trade or business by which any scheduled commodity is taken out of the country;
"fee" means the rate designated by the Commission as certificate fee for radioactivity analysis and payable under the provisions of these Regulations or in accordance with the Act;
"importer" means any person undertaking trade of business by which any scheduled commodity is brought into the country;
"Minister" means the Minister responsible for matters relating to radiation protection;
"scheduled commodity" means any foodstuff, agricultural produce or thing specified in the First Schedule.
3. Contamination analysis
No human or animal foodstuffs or thing listed in the First Schedule shall be imported, cleared through Customs or distributed for home consumption unless an analysis under the Act has been conducted on such foodstuffs and a certificate has been issued certifying that they are free from radioactive contamination or contain levels of such contamination below the levels prescribed in the Second Schedule.
4. Radioactivity certificate and fees
(1) A radioactivity analysis shall be made and a radioactivity analysis certificate shall be issued in respect of all the commodities specified in the First Schedule and the importer or exporter concerned shall be required to pay such fees as may be determined by the Minister in order to offset the costs of the analysis.
(2) The fees payable under this Regulation are set out in the Third Schedule.
5. Certificates for foodstuffs donated, etc.
All grants, donations or presents of foodstuffs falling under the First Schedule shall be issued with a certificate before they are distributed for consumption and fees shall be levied for the certificate under Regulation 4.
6. Clearance of scheduled foodstuffs
Any person who imports or exports any scheduled commodity shall produce a certificate in respect of every consignment prior to inward or outward clearance through customs as the case may be.
7. Sampling
(1) All importers and exporters including Government departments and Non-Government Organizations shall make available to the Commission adequate samples of the scheduled commodities they wish to export or import, and no clearance through Customs shall be effected unless and until a certificate has been issued in respect of commodities.
(2) The sampling of commodities under these Regulations shall be made according to procedures and form set out in the Third and Fourth Schedules.
8. Duty to comply with directions of Commission
Every importer and exporter of any scheduled commodity shall comply with such directions as the Commission may give in order to facilitate the issuance of a certificate.
9. Offences and penalties
Any person who contravenes any provision of these Regulations or fails to comply with any direction given by the Commission shall be guilty of an offence and shall on conviction be liable to a fine not exceeding seven thousand shillings or its equivalent in US dollars or to a prison term not exceeding six months or to both such fine and imprisonment.
10. Restriction on importing contaminated foods
(1) No foodstuffs specified in the First Schedule shall be imported or cleared for home consumption where the radiation levels exceed the limits indicated in the Second Schedule or as revised from time to time.
(2) Any imported foodstuffs or commodities found contaminated in excess of the levels referred to in subregulation (1) shall be refused entry and shall be destroyed or returned to the country of origin at the expense of the importer.
11. Alteration of fees
The Minister may on recommendations from the Commission after the fees to be paid under these Regulations by order published in the Gazette.
FIRST SCHEDULE
DESCRIPTION OF COMMODITY
(Regulation 3)
Milk (all types of milk and milk products) |
Meat (all types of meat and meat products) |
Fish (all types of fish and marine foods) |
Fruits and fruit products |
Vegetables and edible oils |
Wheat and wheat products |
Tea |
Rice |
Mushrooms |
Tobacco |
Animal feeds of all types |
Beans |
Maize and maize products and all types of cereals |
Coffee and coffee products |
Fertilizers |
Biscuits, chocolates and sweets |
Barley and barley products |
Infant foods |
Salt and sugar |
Spices |
All types of human foods not listed above. |
SECOND SCHEDULE
INTERVENTION LEVELS FOR CONTROL OF FOODSTUFFS:
JOINT WHO/IAEA STANDARDS
(Regulation 3)
Levels for beta/gamma emitters: Bq/kg or Bq/li levels for actinides are shown in brackets.
Joint WHO/IAEA Standards
Foodstuffs | Level |
|
1. Milk and infant foods ........................................................ | Sr–90 | 100 |
2. All other foods ................................................................. | Sr–90 | 1000 |
Total gamma ..................................................................... | 1000 | (10) |
NB. WHO means the United Nations World Health Organisation.
IAEA means the international Atomic Energy Agency.
THIRD SCHEDULE
FEES
(Regulation 4(3))
Per consignment of net weight not exceeding 5 tonnes ........ | Shs. 100,000/- |
Per consignment of net weight exceeding 5 tonnes ............. | Shs. 50,000/- plus |
| Shs. 50,000/- for every additional 5 tonnes or part thereof |
FOURTH SCHEDULE
RECOMMENDED PROCEDURES FOR SAMPLING AND SAMPLE HANDLING
(Regulation 7(2))
Sampling is one of the most common sources of analytical error. The results of analysis will be meaningful only if the sub-sample analyzed is representative of the sample submitted for analysis and the sample submitted is representative of the bulk of material sampled. |
1. Recommended Procedures for Sampling and Sample Handling: |
(a) It is recommended that random sampling should be done on the whole bulk of the (material) consignment intended for export or import, by taking as may sub-samples as possible from various points of the consignment and combine the sub-samples together to make a representative sample of 1-2 kg for solid/powder samples and/or 1-2 litres for liquid samples. |
(b) The quantity of the representative sample shall be based on the net amount of the whole material in the consignment intended for export or import. It is recommended that at least a total of 2 kg of the material has to be sampled from each (500,000 kg) or 1000 packs of the same material in the consignment, and at least 5 tinned, bottled or boxed material has to be sampled from each 100 (package packs of the same material in the consignment. |
(c) Sample collection equipment, containers and sample preparation areas must be kept clear to avoid contamination. |
(d) Disposable containers should be used whenever possible (plastic bags, aluminium foils, etc.) are recommended for collection of samples. |
(e) In order to avoid cross contamination of samples, it is important that all samples collected for radioactivity analysis be packed into tight containers such as polyethylene bags or plastic/grass containers with screw caps. It is further recommended that liquid samples should be packed separately and if possible overpacks may be used. |
(f) Collected (representative) samples must be submitted to the NRC laboratory at least 2-3 days after the end of a sampling process. |
(g) When samples are taken, a label should be prepared and attached to the sample container. The label should contain the information: Sample description, Sample location (where it was sampled), Time and date where the sample was taken, Amount of sample (in kg or litres) fresh weight, Name of the person who took the sample, as shown in First Schedule. |
(h) For each sample taken, packed and prepared for delivery to NRC for radioactivity analysis, the form in the Fifth Schedule Part B should be filed with particulars of the consignment, signed and submitted with the respective samples. |
2. Recommendations for Storage of Sample(s): |
Samples must be handled in a manner which prevents or minimises changes. This is essential, particularly if many types of food involved are perishables. |
(a) After collection the samples must be properly stored to avoid degradation, spoiling or other decomposition and to avoid contamination. |
(b) Short periods of storage before analysis may require refrigeration, freezing or addition of a preservative. Fresh milk is usually stored in a refrigerator. A preservative such as formalin or sodium azide (3-5 ml of 5% solution per litre) can be added to prevent souring if longer periods of storage is anticipated. |
(c) Sample containers must be suitable for storage without degeneration especially when acids are added to liquid samples. Absorption of most radionuclides from solutions is less in polyethylene than on glass. |
FIFTH SCHEDULE
SAMPLE RECORD FORM
Regulation 7(2)
(A) Sample record/sample label data: |
|
1. Sample identity/mark. |
|
2. Sample description. |
|
3. Sample location (where it was sampled). |
|
4. Amount of sample (in kg or litres) fresh weight. |
|
5. Time and date when the sample was taken. |
|
6. Name of person who took the sample. |
|
(B) Particulars of Consignment as Declared by Exporter/Importer: |
|
(i) Description of Goods/Articles: ........................................................................... |
|
(ii) Quantity:.......................................................................................................... |
|
(iii) Consignment No. |
|
(iv) Exporter/Shipper: ............................................................................................. |
|
(v) Consignee: ...................................................................................................... |
|
(vi) Shipping Vessel: .............................................................................................. |
|
(vii) Point of Exit/Entry: ........................................................................................... |
|
(viii) Destination: ..................................................................................................... |
|
Comments: |
|
Declaration: |
|
I ....................................................................................... declare that the representative samples to the particulars above have been taken by me in accordance with the procedures in the Fourth Schedule and to the best of my knowledge this is a true representative sample of the consignment above. |
|
Name and Signature: ......................................... | Date: .............................. |
ARRANGEMENT OF REGULATIONS
Regulation
Title
PART I
PRELIMINARY
1. Short title.
2. Interpretations.
3. Application.
4. Radioactive waste classification.
PART II
RESPONSIBILITIES, DUTIES AND ADMINISTRATIVE MEASURES
5. Responsibilities of a regulatory body.
6. Function of the Central Radioactive Waste Management Facility.
7. Responsibilities of the waste generator.
8. Responsibilities of Radioactive Material Coordinator.
9. Licence applications and requirements.
10. Return of sources to supplier.
11. Modification.
12. Public involvement.
PART III
WASTE MANAGEMENT OPERATIONS
13. Segregation, collection and characterisation.
14. Container labelling.
15. Procedure for discharge of radioactive substance to the environment.
16. Discharge of exempt waste.
17. Release of specific waste.
18. Waste storage.
19. Preparation for transportation of waste.
20. Transportation.
21. Treatment.
22. Conditioning.
23. Disposal of radioactive waste.
24. Quality assurance.
25. Physical protection.
PART IV
REPORTING TO THE REGULATORY BODY
26. Inventory and reporting.
27. Emergency preparedness.
PART V
FINANCING
28. Financial obligation.
PART VI
VERIFICATION AND ENFORCEMENT
29. Right of entry and inspections.
PART VII
OFFENCES AND PENALTIES
30. Failure to produce a licence
31. Obstructions.
32. Other offences.
33. Offences by body corporate.
34. Appeals.
SCHEDULES
RADIOACTIVE WASTE MANAGEMENT FOR THE PROTECTION OF HUMAN HEALTH AND ENVIRONMENT REGULATIONS
(Section 40(1))
[17th September, 1999]
G.N. No. 276 of 1999
PART I
PRELIMINARY PROVISIONS (regs 1-4)
1. Short title
2. Interpretations
3. Application
(a) all solid, liquid and gaseous waste with activity levels above the clearance levels specified in the Second Schedule in Table II-1B;
(b) all users of sources of ionising radiation in medicine, industry, teaching, research, agriculture, hydrology, geology and other fields of human activity whenever such uses are subject to licensing under these Regulations;
(c) operators of radioactive waste management facilities other than the regulatory body.
4. Radioactive waste classification
(a) According to its physical form and composition:
(i) Combustible waste;
(ii) non-combustible waste;
(iii) compactible waste;
(iv) non-compactible waste;
(v) liquid aqueous waste;
(vi) liquid organic waste;
(vii) gaseous waste;
(viii) sealed radiation sources;
(ix) biological waste (like animal carcasses which might undergo decomposition if not properly treated and stored);
(x) medical waste (e.g. syringes, bed linen and contaminated clothing from a hospital environment);
(b) according to the activity concentration and half lives of radionuclides contained in the radioactive waste:
(i) low level radioactive waste (e.g. the activity is less than 10 MBq), containing short lives radionuclides only (e.g. with half-life less than 50 days) that will decay to clearance levels within one year after the time of its generation. Disposal is by discharge after reaching clearance levels;
(ii) low and intermediate level radioactive waste, containing the radionuclides with half life less than or equal to thirty years and restricted long lived radionuclide concentrations and that is not expected to decay to clearance levels within one year from the time of its generation (limitation of longer lived apha-emitting radionuclides to 4000 Bq/g in individual waste packages and to an overall of 400 Bq/g per waste package). This waste needs to be disposed of at a near surface or geological disposal facility;
(iii) low and intermediate level radioactive waste, containing the radionuclides with half life greater than 30 years, and concentration of alpha emitters exceeding the limitations under paragraph (ii) above. This waste needs to be disposed of in deep geological facilities only;
(iv) high level radioactive waste, with thermal power above 2kW/m3 and concentration of alpha emitters exceeding the limitations for paragraph (ii) above (e.g. spend fuel from research reactors). This waste needs to be disposed of in a deep geological facility only.
PART II
RESPONSIBILITIES, DUTIES AND ADMINISTRATIVE MEASURES (regs 5-12)
5. Responsibilities of a regulatory body
6. Functions of the Central Radioactive Waste Management Facility
7. Responsibilities of the waste generator
8. Responsibilities of Radioactive Material Co-ordinator
(a) To establish, maintain and keep up-to-date an inventory of radioactive materials and generated waste;
(b) to make and maintain contact with all on-site persons using radioactive materials and provide an authoritative point of advice and guidance;
(c) to liaise as needed with the Central Radioactive Waste Management Facility authority;
(d) to establish and maintain a record keeping system in such a manner as to facilitate identification, characterisation, collection and storage of radioactive materials that become waste;
(e) ensure that on-site transfer of radioactive materials and waste Is carried out in accordance with written safety procedures;
(f) to ensure that preparation of waste for transport to the Central Radioactive Waste Management Facility meets Transport Regulations as provided for under paragraphs (1) and (2) of regulation 20;
(g) to ensure appropriate shielding, labelling, physical security and integrity of waste packages;
(h) to ensure that any discharge of effluent is made within clearance levels or authorised limits;
(i) to ensure that the disposal of solid waste to a local dump site is below clearance levels;
(j) to report on accidents and inappropriate waste management practices to the facility management.
9. Licence applications and requirements
(a) Nature and purpose of the proposed facility and equipment that generates radioactive waste;
(b) suggested operational procedures, taking into consideration reduction of radioactive waste generation to the extent practicable;
(c) quantity, type and characteristic of the radioactive waste to be generated;
(d) proposed destination for the radioactive waste;
(e) safety analysis report and environmental impact assessment of the facility both under normal and accident conditions;
(f) decommissioning procedures;
(g) availability of competent staff and provisions for its further training;
(h) systems for records keeping and reporting;
(i) proposed quality assurance programme;
(j) contingency plans in the event of an emergency;
(k) proposals for discharge and environmental monitoring as needed;
(l) supporting research and development proposals as needed;
(m) such other details as the regulatory body may consider necessary.
(a) valid for such a period as the regulatory body may determine;
(b) renewable by the regulatory body if the licensee complies with the licence conditions;
(c) subject to supervision or revocation as notified in writing if in the view of the regulatory body, the licensee has failed to comply with licence conditions.
10. Return of sources to supplier
(a) require the supplier, as a condition of purchase or of any gift, to receive the source back after its useful lifetime within one year of the recipient requesting such return, provided that the recipient seeks to return the source to the supplier not later than 15 years after purchase or receipt;
(b) submit to the regulatory body a copy of relevant parts of the contract or acceptance document and obtain its written agreement prior to entering;
(c) return the source to the supplier within 15 years or if later send it to the Central Radioactive Waste Management Authority for any conditioning, and storage at the cost of the waste generator.
11. Modification
12. Public involvement
PART III
WASTE MANAGEMENT OPERATIONS (regs 13-25)
13. Segregation, collection and characterisation
(a) be easy to handle;
(b) be strong enough to withstand normal handling;
(c) not be affected by the waste content.
14. Container labelling
(a) nature of the waste generated (as prescribed in paragraph (a) of regulation 4);
(b) date of waste generations;
(c) commencement date of storage;
(d) content of major radiological significant radionuclides;
(e) external surface dose rate;
(f) waste category;
(g) biological, chemical or other hazardous materials if they exist;
(h) name of a person or organisation responsible for the waste generation;
(i) identification number; and
(j) any other particular information that may be required by the regulatory body.
15. Procedure for discharge of radioactive substance to the environment
(a) the waste activity or concentration have been confirmed to be below clearance levels as prescribed Table Il-1B of the Second Schedule;
(b) discharge of liquid or gaseous effluents is within the limits authorised by the regulatory body;
(c) the discharge or release of liquid effluent under subparagraph (b) above shall take into consideration the following:
(i) Acidic waste to be neutralised and, if necessary, filtered before they are discharged into the sewage system;
(ii) on each release occasion flushing shall be carried out with considerable quantities of water;
(iii) release of radioactive waste shall be confined to one release point for each laboratory. The release point shall be marked by a visible sign showing that radioactive waste may be released into the sewage system;
(iv) patients who have been administered radionuclides in connection with diagnosis or treatment shall use a separate toilet, marked and identified for that purpose, and that flushing to be adequate after each use;
(v) non-aqueous waste or immiscible liquid waste shall not be discharged into sewers.
(a) determine the characteristics and activity of the material to be discharged, and the potential points and methods of discharge;
(b) determine by an appropriate pre-operational model study, significant exposure pathways by which discharge radionuclides shall deliver public exposure;
(c) assess the doses to the critical groups due to the planned discharges;
(d) submit this information to the regulatory body as an input to the establishment of authorised discharge limits and conditions for their implementation.
(a) keep all radioactive waste discharge below authorised discharge limits;
(b) monitor the discharges of radionuclides with sufficient detail and accuracy to demonstrate compliance with the authorised discharge limits and to permit estimation of the exposure of critical groups;
(c) record the monitoring results;
(d) report promptly to the regulatory body any discharges exceeding the authorised discharge limits in accordance with reporting criteria established by the regulatory body.
16. Discharge of exempt waste
17. Release of specific waste
(a) 0.05µCi (1.85Bq), or less of hydrogen 3 or carbon 14 per gram of medium waste used for liquid scintillation counting; and
(b) 0.05µCi (1.85Bq), or less of hydrogen 3 or carbon 14 per gram of animal tissue, averaged over the weight of the entire animal.
18. Waste storage
(a) Adequate shielding of the radioactive waste;
(b) prevention of deterioration of waste packages;
(c) handling retrievability waste packages;
(d) adequate ventilation if volatile radioactive substances may be present in the waste;
(e) conventional safety;
(f) physical protection.
19. Preparation for transportation of waste
20. Transportation
(a) The radioactive waste packages shall be transported in containers or special vessels using a special car;
(b) waste transporting car shall not be used for public transport;
(c) the car shall be covered and the internal walls be painted such that it can be easily decontaminated;
(d) the car shall be provided with loading and unloading means.
21. Treatment
22. Conditioning
23. Disposal of radioactive waste
24. Quality assurance
25. Physical protection
PART IV
REPORTING TO THE REGULATORY BODY (regs 26-27)
26. Inventory and reporting
(a) the exempt waste disposed of at a local dumping site, sewer system or to the atmosphere;
(b) the effluents discharged into the environment within authorised release limits;
(c) the conditioned radioactive waste in storage;
(d) the conditioned radioactive waste dispatched to a disposal facility;
(e) the spent radiation sources, sent to supplier.
27. Emergency preparedness
(a) deal with any emergency involving Radioactive Waste at their Facilities. The procedure shall also, when appropriate, include unplanned events outside the normal working area, for instance during transportation; and
(b) inform the regulatory body without delay of any emergency in relation to radioactive waste.
PART V
FINANCING (reg 28)
28. Financial obligation
PART VI
VERIFICATION AND ENFORCEMENT (reg 29)
29. Right of entry and inspections
PART VII
OFFENCES AND PENALTIES (regs 30-34)
30. Failure to produce a licence
31. Obstructions
32. Other offences
33. Offences by body corporate
34. Appeals
FIRST SCHEDULE
DISCHARGE OF RADIOACTIVE WASTE
Waste may be released into the atmosphere, discharged into the public sewer system, incinerated in an incinerator or sent for disposal into a local dump site provided, that annual limits of intake indicated below are not exceeded. There are different ALI values for oral intake as opposed to inhalation. ALI minimum (ALI
Table II-1B of the Second Schedule gives the numerical values of ALI
1. If the waste in solid, liquid and gas contains more than one radionuclide the highest permitted activity per year shall be calculated in accordance with equation (1). The total activity, however, shall not exceed 5MBq per year. ALI> A> ALI> 2. If the waste in solid, liquid or gas contains more than one radionuclide the highest permitted activity per month shall be calculated in accordance with equation (2). The total activity however, shall not exceed 1 ALI> ALI> The total activity, however, shall not exceed 5MBq per year 3. If the waste in solid, liquid or gaseous form contains more than one radionuclide then the highest activity in one individual discharge shall be calculated in accordance with equation (3). The maximum activity in each waste package or per release shall not exceed 0.1ALI> ALI> Note: (a) The dose rate at a surface of the solid waste package to be sent to a local dump site shall not exceed 5 Sv/h. (b) For solid waste, equation 3 applies only for a single individual waste package. (c) When a waste package is to be sent to an incinerator or dump site the package shall carry the following information– Records of discharged exempt waste shall be established by the waste generator and kept for at least ten years. The records shall be available for inspection by the regulatory body. |
SECOND SCHEDULE
A. OCCUPATIONAL MINIMUM ANNUAL LIMITS ON INTAKE ALI>
OF RADIONUCLIDE BY WORKERS BASED ON THE 1990 RECOMMENDATION
AS GIVEN IN ICRP PUBLICATION 61 VOL 21 No. 4
According to its definition, the ALI value is the activity which if inhaled or ingested would result in a dose of 20 mSv/year (ICRP 60). This dose is the annual limit of intake for radiation workers. Table II-1A gives a list of intakes for the most frequently used radionuclides reading to doses of 20mSv. The values in the smaller of the ALI values for ingestion or inhalation.
NB: "ICRP" means "International Commission on Radiological Protection".
Table II-1A (Occupational ALI>
NUCLIDE | Bq |
H - 3 Water | 1.00E+09 |
C - 14 | 4.00E+07 |
F - 18 | 4.00+08 |
Na - 22 | 1.00E+07 |
Na - 24 | 5.00E+07 |
P - 32 | 8.00E+06 |
P - 33 | 8.00E+07 |
S - 35 | 1.00E+08 |
CI - 36 | 2.00E+07 |
CI - 38 | 2.00E+08 |
K - 40 | 4.00E+06 |
K - 42 | 5.00E+07 |
K - 43 | 9.00E+07 |
45 Ca | 1.00E+07 |
Ca - 47 | 1.00E+07 |
Cr - 51 | 5.00E+08 |
Mn - 51 | 1.00E+07 |
Mn - 52 | 3.00E+08 |
Mn - 54 | 2-00E+07 |
Mn - 56 | 2.00E+07 |
Fe - 52 | 1.00E+07 |
Fe - 55 | 3.00E+07 |
Fe - 59 | 5.00E+06 |
Co - 56 | 3.00E+06 |
Co - 57 | 3.00E+07 |
Co - 58 | 1.00E+07 |
Co - 60 | 2.00E+06 |
Ni - 63 | 2.00E+07 |
Cu - 64 | 2.00E+08 |
Cu - 67 | 5.00E+07 |
Zn - 62 | 2.00E+07 |
Zn - 65 | 4.00E+06 |
Zn - 69m | 5.00E+07 |
Ga - 67 | 8.00E+07 |
Ga - 68 | 2.00E+08 |
As - 73 | 2.00E+07 |
As - 74 | 9.00E+06 |
Se - 75 | 9.00E+06 |
Br - 76 | 5.00E+07 |
Br - 77 | 2.00E+08 |
Br - 82 | 4.00E+07 |
Rb - 81m | 2.00E+09 |
Rb - 81 | 4.00E+08 |
Rb - 86 | 8.00E+06 |
Rb - 88 | 2.00E+08 |
Rb - 89 | 4.00E+08 |
Sr - 85m | 4.00E+09 |
Sr - 87m | 7.00E+06 |
Sr - 90 | 4.00E+05 |
Y - 90 | 5.00E+06 |
Tc - 99m | 1.00E+09 |
Tc - 99 | 1.00E+09 |
Mo - 99 | 3.00E+07 |
In - 113m | 9.00E+08 |
Sb - 124 | 6.00E+06 |
I - 123 | 9.00E+07 |
I - 125 | 1.00E+06 |
I - 129 | 2.00E+05 |
I - 130 | 1.00E+07 |
I - 131 | 8.00E+05 |
I - 132 | 7.00E+07 |
Cd - 109 | 1.00E+06 |
Cd - 115 | 1.00E+07 |
In - 111 | 5.00E+07 |
Cs - 129 | 3.00E+08 |
Cs - 130 | 7.00E+08 |
Cs - 131 | 3.00E+08 |
Cs - 134 | 1.00E+06 |
Cs - 134m | 1.00E+09 |
Cs - 137 | 1.00E+06 |
Ba - 131 | 4.00E+07 |
Ba - 133m | 3.00E+07 |
Ba - 135m | 4.00E+07 |
La - 140 | 8.00E+06 |
Yb - 169 | 1.00E+07 |
Ir - 192 | 6.00E+06 |
Au - 198 | 1.00E+07 |
Hg - 197 | 6.00E+07 |
Hg - 203 | 2.00E+07 |
TI - 201 | 3.00E+08 |
TI - 204 | 3.00E+07 |
Pb - 210 | 1.00E+04 |
Pb - 212 | 5.00E+05 |
Po - 210 | 2.00E+04 |
Ra - 226 | 9.00E+03 |
Th - 232 | 9.00E+01 |
U - 238 | 9.00E+04 |
Am - 241 | 3.00E+02 |
Cm - 244 | 5.00E+02 |
Cf - 252 | 9.00E+02 |
B. ANNUAL LIMITS OF INTAKE BY MEMBERS OF THE PUBLIC
FOR THE COMMONLY USED RADIONUCLIDES AS DERIVED
FROM ANNUAL LIMITS OF INTAKE BY WORKERS
BASED ON THE ICRP PUBLICATION 61 Vol 21 No. 4
In order to ensure that radiation doses to individual members of the public are very small, quantities of radionuclides released have to be limited to amounts that if total, ingested or inhaled, would not result in doses greater than the exempt dose of 10µSv/year. In practice, these quantities are framed as some fraction of the Annual Limit of Intake (ALI) introduced by the International Commission on Radiological Protection (ICRP) for either ingestion or inhalation. Hence, 0.05% of the ALI for workers would result in a dose of ten microsievert (10µSv). Thus the total intake approach results in a derived exemption level of 0.05% of the smaller of the ALI values for inhalation or ingestion given in Table II-1A.
Table II-1B gives a list of the total intakes for the frequently used radionuclides leading to a dose of ten (10) microsievert (µSv).
TABLE Il-1B (Waste clearance levels)
NUCLIDE | Bq |
H - 3 Water | 500,000 |
C - 14 | 20,000 |
F - 18 | 200,000 |
Na - 22 | 5,000 |
Na - 24 | 25,000 |
P - 32 | 4,000 |
P - 33 | 40,000 |
S - 35 | 50,000 |
Cl - 36 | 10,000 |
Cl - 38 | 100,000 |
K - 40 | 2,000 |
K - 42 | 25,000 |
K - 43 | 45,000 |
Ca - 45 | 5,000 |
Ca - 47 | 5,000 |
Cr - 51 | 250,000 |
Mn - 51 | 5,000 |
Mn - 52 | 150,000 |
Mn - 54 | 10,000 |
Mn - 56 | 10,000 |
Fe - 52 | 5,000 |
Fe - 55 | 15,000 |
Fe - 59 | 2,500 |
Co - 56 | 1,500 |
Co - 57 | 15,000 |
Co - 58 | 5,000 |
Co - 60 | 1,000 |
Ni - 63 | 10,000 |
Cu - 64 | 100,000 |
Cu - 67 | 25,000 |
Zn - 62 | 10,000 |
Zn - 65 | 2,000 |
Zn - 69m | 25,000 |
Ga - 67 | 40,000 |
Ga - 68 | 100,000 |
As - 73 | 10,000 |
As - 74 | 4,500 |
Se - 75 | 4,500 |
Br - 76 | 25,000 |
Br - 77 | 100,000 |
Br - 82 | 20,000 |
Rb - 81m | 1,000,000 |
Rb - 81 | 200,000 |
Rb - 86 | 4,000 |
Rb - 88 | 100,000 |
Rb - 89 | 200,000 |
Sr - 85m | 2,000,000 |
Sr - 87m | 20,000 |
Sr - 90 | 3,000 |
Y - 90 | 2,500 |
Tc - 99m | 500,000 |
Tc - 99 | 500,000 |
Mo - 99 | 15,000 |
In - 113m | 450,000 |
Sb - 124 | 3,000 |
I - 123 | 45,000 |
I - 125 | 500 |
I - 129 | 100 |
I - 130 | 5,000 |
I - 131 | 400 |
I - 132 | 35,000 |
Cd - 109 | 500 |
Cd - 115 | 5,000 |
In - 111 | 25,000 |
Cs - 129 | 150,000 |
Cs - 130 | 350,000 |
Cs - 131 | 150,000 |
Cs - 134 | 500 |
Cs - 134rn | 500,000 |
Cs - 137 | 500 |
Ba - 131 | 20,000 |
Ba - 133m | 15,000 |
Ba - 135m | 20,000 |
La - 140 | 4,000 |
Yb - 169 | 5,000 |
Ir - 192 | 3,000 |
Au - 198 | 5,000 |
Hg - 197 | 30,000 |
Hg - 203 | 10,000 |
TI - 201 | 150,000 |
TI - 204 | 15,000 |
Pb - 210 | 5 |
Pb - 212 | 250 |
Po - 210 | 10 |
Ra - 226 | 4.5 |
Th - 232 | 0.045 |
U - 238 | 45 |
Am - 241 | 0.15 |
Cm - 244 | 0.25 |
Cf - 252 | 0.45 |
THIRD SCHEDULE
A. PRINCIPAL NUCLIDES USED IN MEDICINE,
CLINICAL MEASUREMENTS AND BIOLOGICAL RESEARCH
As a guideline to the proper waste management procedures Table III-A below gives a list of principal radionuclides used as open sources in life sciences. The half life, principal application, typical quantities per application and emanating waste types have been projected for each radionuclide listed. It is hoped that such a guideline will be a good tool towards the implementation of effective radioactive waste management practices.
RADIO- | HALF | PRINCIPAL | TYPICAL QUANTITY PER APPLICATION | WASTE TYPES |
12.26a | Clinical measurements Biological research Labelling | Up to 5 MBq | Solid, liquid |
|
5950a | Biological research labelling | Less than 1 GBq | Solid, liquid |
|
2.6a | Clinical measurements Biological research | Up to 50 kBq | Solid, liquid |
|
15h | Clinical measurements | Up to 5 GBq | Liquid |
|
14.3d | Therapy Biological research | Up to 200 Bq | Solid, liquid |
|
87.4d | Clinical measurements | Up to 5 GBq | Solid, liquid |
|
3.01x | Biological research | Up to 5 MBq | Gaseous solid |
|
164d | Biological research | Up to 100 MBq | Mainly solid |
|
27.7d | Clinical research Biological research | Up to 5Mbq | Mainly liquid |
|
271.7d | Clinical measurements | Up to 50 kBq | Solid, liquid |
|
44.6d | Clinical Measurement | Up to 50 MBq | Mainly liquid |
|
6.0h | Clinical measurement | Up to 600 MBq | Solid, liquid |
|
78.26h | Clinical measurements | Up to 200 MBq | Liquid |
|
119.8d | Clinical measurements | Up to 11 MBq | Solid, liquid |
|
64.8d | Clinical measurements | Up to 50 MBq | Solid, liquid |
|
64h | Therapy | Up to 120 MBq | Solid, liquid |
|
2.8d | Therapy | Up to 1500 MBq | Solid, liquid |
|
2.8d | Clinical measurements | Up to 500 MBq | Solid, liquid |
|
13.2h | Clinical measurement | Up to 800 MBq | Solid, liquid |
|
5.25d | Clinical measurements | Up to 200 MBq | Gaseous |
|
30.1a | Therapy | Up to 500 TBq | Solid |
|
3.02d | Clinical measurements | Up to 120 MBq | Solid, liquid |
|
74d | Sealed source therapy | Up to 500 GBq | Solid |
|
64.4h | Clinical measurements | Up to 50 MBq | Solid, liquid |
|
2.7d | Clinical therapy | Up to 10 GBq | Liquid |
|
433a | Clinical measurements | Up to 10 GBq | Solid |
B. PRINCIPAL NUCLIDES USED IN SEALED RADIATION SOURCES
IN INDUSTRY AND RESEARCH
As a guide towards effective radioactive waste management practices Table III-B below gives a list of the principal radionuclides used as sealed resources in industry and research. The half life, principal application and the typical as spent sealed sources and waste management practices must be dealt with accordingly.
RADIONUCLIDE | HALF- LIFE | PRINCIPAL APPLICATION | TYPICAL ACTIVITY PER SOURCE |
12.3a | Light sources, electron capture detectors, targets, electronic valves. | From kBq up to 10 TBq |
|
2.6a | X-ray fluorescence | Up to 5 GBq |
|
271.7d | Calibration sources | Up to 100 MBq |
|
5.3a | Radiography, irradiators | Up to 400 PBq |
|
100a | Electron capture detectors | Up to 50 GBq |
|
10.76a | Thickness gauges, electronic valves | Up to 100 GBq |
|
28.1a | Thickness and density gauges | Up to 10 GBq |
|
2.1a | Density gauges | Up to 20 GBq |
|
30a | Radiography, irradiators, density and level gauges, well-logging | Up to 400 PBq |
|
2.62a | Thickness gauges, light sources | Up to 2 GBq |
|
32d | Radiography | Up to 1 TBq |
|
128.6d | Radiography | Up to 1 TBq |
|
74d | Radiography | Up to 5 TBq |
|
138d | Static eliminators | Up to 20 GBq |
|
87.7a | X-ray fluorescence analysis | Up to 5 GBq |
|
433a | Density, level and thickness gauges, X-ray fluorescence, well-logging, moisture detectors | Up to 500 GBq |
|
2.6a | Moisture detectors, neutron sources | Up to 10 GBq |
FOURTH SCHEDULE
USEFUL RADIOACTIVE MATERIAL AND RADIOACTIVE WASTE INVENTORY REPORTING FORM
As required under part IV of Regulation 26 of these Regulations a licensee shall prepare a report on radioactive waste and submit it to the regulatory body as appropriate. This form is intended to meet such a requirement and it should be duly completed by each licensee.
Monthly/Quarterly/Annual Reports
PERIOD: From .................................. to .........................................
NAME OF INSTITUTION ..................................................................
1. RADIOACTIVE MATERIALS RECEIVED
1.1: Sealed Sources
Date Recv | Nuclide | Activity and reference date | Supplier or Manufacturer | Identity Sr/No. | Location or room | Application or use |
If space is not sufficient use additional sheets
1.2 Unsealed resources
Date Recv | Nuclide | Activity and reference date | Supplier | Batch No. | Quantity (cm> | Location | Application or use |
2. RADIOACTIVE MATERIAL(S) IN STOCK/CURRENTLY IN USE
2.1 Unsealed source
Nuclide | Activity and reference date | Supplier | Batch No. | Quantity (cm> | Location or room | Remarks |
3. RADIOACTIVE WASTE IN STORAGE
3.1 Solid radioactive waste eminating from unsealed source(s)
3.1.1 Combustible
Radionuclides | Radionuclides contained | Quantity per container (cm> | Materials of the container | Activity in container (give ref. date) | Waste types | Storage location |
3.1.2 Non-Combustible
Radio nuclides | Radio nuclides contained | Quantity per container (cm> | Materials of the container | Activity in container (give ref. date) | Waste types | Storage location |
3.1.3. Compactible
Radionuclides | Radionuclides contained | Quantity per container (cm> | Materials of the container | Activity in container (give ref. date) | Waste types | Storage location |
3.1.4 Non-compactible
Radionuclides | Radionuclides contained | Quantity per container (cm> | Materials of the container | Activity in container (give ref. date) | Waste types | Storage location |
3.2 Sealed spent sources
Nuclide | Activity/ref. Date | Supplier or manufacturer | Identity/Sr/No. | Former application | Storage location |
3.3 Liquid radioactive waste
3.3.1 Aqueous Liquid Waste
Identity number of container | Material of the container | Quantity of waste (cm> | Activity and Reference date | Indicate whether acidic or alkaline | Radio nuclides in container |
3.3.2 Organic liquid waste
Identity number of container | Material of the container | Quantity of waste (cm> | Activity and Reference date | Indicate whether acidic or alkaline | Radio nuclides in container |
4. RADIOACTIVE WASTE DISCHARGES
4.1 Combustible Waste
Month | Quantity in cm> | Principal Radio- | Place of discharge | Method of discharge | Total activity discharged | Discharge allowed by |
4.2 Non-Combustible Waste
Month | Quantity in cm> | Principal Radio- | Place of discharge | Method of discharge | Total activity discharged | Discharge allowed by |
4.3 Compactible Waste
Month | Quantity in cm> | Principal Radio- | Place of discharge | Method of discharge | Total activity discharged | Discharge allowed by |
4.4 Non-Compactible Waste
Month | Quantity in cm> | Principal Radio- | Place of discharge | Method of discharge | Total activity discharged | Discharge allowed by |
4.5 Sealed spent sources returned to supplier or transferred to another user. Please complete as required below.
Date on which source was returned or transferred | Address of person/ | Radionuclides | Activity and Reference date | Former application | Return/ |
4.6 Aqueous Radioactive Waste
Month | Quantity in cm> | Principal radionuclides | Place and or method of discharge | Total activity discharge | Discharge authorised by |
4.7 Organic Radioactive Waste
Month | Quantity in cm> | Principal radionuclides | Place and or method of discharge | Total activity discharge | Discharge authorised by |
REMARKS:
If you have any remarks/comments please write them in the space below– ................................................................................................................................. |
|
DECLARATION: | |
I ............................................................................................................... declare that the information on this form to the best of my knowledge is true and correct. |
|
Name: ............................................................................................................................ |
|
Signature and Official Stamp: ........................................................................................... |
|
Position: ...................................................................... Date: .......................................... |
FIFTH SCHEDULE
APPLICATION FOR LICENCE/AUTHORISATION TO STORE
AND/OR DISCHARGE RADIOACTIVE WASTES
UNITED REPUBLIC OF TANZANIA
NATIONAL RADIATION COMMISSION
P.O. BOX 743 | For official use only |
APPLICATION FOR LICENCE/AUTHORISATION TO STORE AND/OR DISCHARGE RADIOACTIVE WASTES |
|
1. Application details |
|
Name and address of applicant |
|
2. The premises |
|
2.1 The location of premises from which generation, storage or discharge of radioactive waste is expected. |
|
2.1.1. Generation ................................................................................................. |
|
2.1.2. Storage ..................................................................................................... |
|
2.1.3 Discharge .................................................................................................. |
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2.2. What are the premises used for? (indicate specific purpose (s) in which radioactive materials are used ............................................................................................ |
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2.3. Name and qualifications of the Radioactive Materials Co-ordinator (RMC) |
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3. Radioactive Waste |
|
3.1. General |
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3.1.1. How is radioactive waste produced? ............................................................ |
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3.1.2. What steps will you take to minimise the production of radioactive waste? |
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3.1.3. Will the production of radioactive waste be continuous or for a limited time? |
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If limited, give length of time ( ) Year ( ) month |
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3.2. Solid Radioactive Waste |
|
3.2.1. Do you generate solid radioactive waste? YES [ ] NO [ ] |
|
If yes, answer the following questions: |
|
What are the physical properties of the generated solid waste (e.g inflammable, biologically hazardous etc)? |
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3.2.2. What are the expected volumes per month or year in m |
|
3.3. Liquid Radioactive Waste |
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(a) Aqueous Radioactive Waste |
|
3.3.1. Are you going to generate any aqueous radioactive waste? |
|
If no, go to section 3.3(6). |
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3.3.2. What are the main chemical and physical properties of the liquid? |
|
3.3.3. What radionuclides are expected to exist in the waste? |
|
3.3.4. What is estimated monthly maximum volume of aqueous radioactive waste resulting from operations or processes before being diluted with other liquid waste? |
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3.3.5. Do you intend to perform controlled release of some aqueous radioactive waste into the public sewer? |
|
YES [ ] NO [ ] |
|
If Yes, | |
...................................................................................................... ...................................................................................................... |
|
3.3.6 Does the system under your control, through which radioactive waste is discharged, operate by gravity (without temporary hold up tanks etc)? YES [ ] NO [ ] If No, give details of delay/dilution tanks, pumps, holding tanks, high level alarm etc. ............................................................................................................... |
|
3.3.7 Is this discharge system completely enclosed in engineered structure? YES [ ] NO [ ] In either case, give details of the system. |
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(May use additional of sheets if necessary) |
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3.3.8 Give the name of the sewer system to which your discharge flows and indicate whether this is private or part of the municipal system. |
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3.3.9 Give the name of the watercourse or water body (e.g. river, lake, ocean) or final destination into which the sewage discharges. |
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(Submit environmental impact assessment) |
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(b) Organic Liquid Radiowaste |
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3.3.10. Are you going to generate any organic liquid radioactive waste? |
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YES [ ] NO [ ] |
|
....................................................................................................... ....................................................................................................... |
|
...................................................................................................... ...................................................................................................... |
4. Storage of Radioactive Waste |
4.1. Do you propose to store radioactive waste on premises? |
YES [ ] NO [ ] |
If No, go to section 5 and sign the declaration. |
If Yes, continue with this section. |
4.2. What are the physical properties of the radioactive waste. |
4.3. What is the maximum activity of each radionuclide to be stored? |
4.4. What is the maximum volume to be stored? [m> |
4.5. What type of containers will be used for the waste? |
4.6. Give details of the place where radioactive waste is going to be stored eg. Building, room, security measures, fire alarm systems and presence of inflammable materials etc. |
4.7. How do you propose to record and label this radioactive waste? Refer to sections 4 and 14 and item 3 of the Fourth Schedule of the Radioactive Waste Management Regulations |
4.8. What is your radiological impact assessment (submit with this application a safety analysis report of your storage facility of the proposed storage of this radioactive waste? [continue on a separate sheet if necessary] |
5. Declaration |
I ......................................................................................................... declare that the information on this form is to the best of my knowledge and belief true and correct. |
Signature of Applicant and Official Stamp ...................................................................... |
Title ........................................................................................................................... |
Date .......................................................................................................................... |
Please send your completed application forms to the address indicated below: |
Registrar, |
{/mprestriction}