Skip to document content Skip to main menu Skip to search

Radioactive Waste Management for the Protection of Human Health and Environment Regulations, 1999

Government Notice 276 of 1999

Radioactive Waste Management for the Protection of Human Health and Environment Regulations, 1999
Citation
Government Notice 276 of 1999
Primary work
Protection from Radiation Act
Date
31 July 2002
Language
English
Type
Government Notice
Collections
Skip to document content
Tanzania
Protection from Radiation Act

Radioactive Waste Management for the Protection of Human Health and Environment Regulations, 1999

Government Notice 276 of 1999

  • Published in Tanzania Government Gazette
  • Commenced on 17 September 1999
  • [This is the version of this document at 31 July 2002.]
  • [Note: This legislation was revised and consolidated as at 31 July 2002 and 30 November 2019 by the Attorney General's Office, in compliance with the Laws Revision Act No. 7 of 1994, the Revised Laws and Annual Revision Act (Chapter 356 (R.L.)), and the Interpretation of Laws and General Clauses Act No. 30 of 1972. All subsequent amendments have been researched and applied by Laws.Africa for TANZLII.]
[Section 40(1); G.N. No. 276 of 1999]
WHEREAS subsection (1) of section 40 of the Protection from Radiation Act1, empowers the Minister on his own motion or upon recommendation or advice by the Commission to make regulations to ensure safety against all radioactive materials and radiation devices which are potentially hazardous for the purpose of this Act:1Cap. 188AND WHEREAS these Regulations are intended to set up the basic technical and organisational requirements to be complied with by waste generators and operators of waste management facilities in order to ensure the protection of human health and the environment from the hazards associated with radioactive waste within and beyond national borders, at present and in future:AND WHEREAS the Commission after preparing the Radioactive Waste Management For Protection of Human Health and Environment Regulations for all persons whose undertakings involve production, treatment, conditioning, storage, transportation and disposal of radioactive waste, and covering requirements associated with such steps in Waste Management as collection, segregation, characterisation and preparation for transport of radioactive waste arising from medical, industrial (but not mining and milling activities) and research facilities where radioactive materials and sources of ionising radiation are produced, used or handled, has recommended to, and advised the Minister:Now THEREFORE, in exercise of these powers, the following Regulations are made:

Part I – Preliminary provisions (regs 1-4)

1. Short title

These Regulations may be cited as the Radioactive Waste Management for the Protection of Human Health and Environment Regulations.

2. Interpretations

In these Regulations, unless the context requires otherwise—"Annual Limit on Intake (ALI)" means the intake of given Radionuclide in a year by reference man which would result in a committed dose equal to the relevant dose limit. The ALI is expressed in units of activity. (According to ICRP 60 an effective dose of 20 mSv shall not be exceeded for occupational workers and of 1 mSv for the public.);"characterisation" means the determination of the physical, chemical and radiological properties of the waste to establish the need for further adjustment, treatment, conditioning, or its suitability for further handling processing, storage or disposal;"clearance levels" means a set of values, established by the regulatory body and expressed in terms of activity concentrations and/or total activities, at or below which sources of radiation can be released from regulatory control;"conditioning" means those operations that produce a waste package suitable for handling, transportation, storage and/or disposal;"container" means the vessel into which the waste form is placed for handling transportation, storage and/or eventual disposal. The waste container is a component of the waste package;"disposal" means the emplacement of waste in an approved, specified facility (e.g. near surface or geological repository) without the intention of retrieval. Disposal may also include the approved direct discharge of effluent into the environment with subsequent dispersion;"exempt waste" In the context of radioactive waste management, waste (from a nuclear facility) that is released from nuclear regulatory control in accordance with clearance levels because the associated radiological hazards are negligible. The designation shall be in terms of activity concentration and/or total activity and may form, mass or value of waste, and its potential use;"licensee" means the holder of a current licence granted for a practice or source who has recognised rights and duties for the practice or source, particularly in relation to protection and safety;"Minister" means the Minister for the time being responsible for matters relating to radiation protection;"monitoring" means the measurement of radiation or radionuclides for reasons related to the assessment or control of exposure and the interpretation of such measurements. Monitoring can be continuous and non-continuous;"nuclear facility" means a facility and its associated land, building and equipment in which radioactive materials are produced, processed, used, handled, stored, or disposed of on such a scale that consideration of safety is required;"quality assurance" means all those planned and systematic actions necessary to provide adequate confidence that an item, process or service will satisfy given requirements for quality, for example, those specified in the licence;"radioactive materials" means a person with appropriate independence and authority appointed by the site management as responsible for radiation safety coordinating purchases, stocking of radioactive materials and the disposal of the waste;"radioactive waste" means material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels as established by the regulatory body, and for which no use is foreseen;"radionuclide" means a nucleus (of an atom) that possesses properties of spontaneous disintegration (radioactivity). Nuclei are distinguished by their mass and atomic number;"regulatory body" means the National Radiation Commission as established by the Act;"repository" means a nuclear facility where waste is emplaced for disposal. Future retrieval of waste from the repository is not intended;"segregation" means an activity where waste or materials (radioactive and exempt) are separated or are kept separate according to radiological, chemical and/or physical properties which will facilitate waste handling and/or processing. It may be possible to segregate radioactive from exempt material and thus reduce the waste volume;"waste form" means the waste in its physical and chemical form after treatment and/or conditioning resulting in a solid product prior to packaging, the waste form is a component of the waste package;"waste generator" means any person or persons or organisation engaged in activities which generate radioactive waste;"waste management" means all the activities, administrative and operational, that are involved in the handling, treatment, conditioning, storage and disposal of waste and it includes transportation;"waste package" means the product of conditioning that includes the waste form and any container(s) and internal barriers (e.g. absorbing materials and line), as prepared in accordance with requirements for handling, transportation, storage and/or disposal.

3. Application

(1)In addition to any existing ionising radiation and nuclear regulations in force at the commencement of these regulations, these Regulations shall apply to—
(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.
(2)These Regulations shall apply throughout Tanzania mainland.

4. Radioactive waste classification

Radioactive waste shall be classified by the following categories:
(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

(1)The regulatory body shall have the power and responsibility for enforcement of compliance of the provisions of these Regulations and any other relevant requirements by waste generators and the implementation of the licensing process for generation and management of radioactive waste.
(2)The regulatory body shall take the responsibility for management of radioactive waste where the waste generator is incapable of appropriate management of the radioactive waste or the licence is revoked, or the waste generator no longer exists. The regulatory body may require to recover the costs incurred from those responsible.
(3)Notwithstanding the provisions of subparagraphs (2) and (4) of regulation 5 of these Regulations, the regulatory body shall have general powers and shall exercise control in all matters regarding safe management of radioactive waste including issuance of licenses connected thereto, suspending or revoking the said licences and or closing down an undertaking established for that purpose if satisfied that the safety of the user or operator or the public is endangered or threatened to be in danger.
(4)The regulatory body shall establish and operate a Central Radioactive Waste Management Facility acronymically called CRWMF.
(5)Without affecting the powers of the regulatory body conferred by these Regulations, the Chief Executive Officer of the regulatory body shall if he deems necessary for the better running, operation and carrying out of the day to day duties of the Central Radioactive Waste Management Facility, appoint such number of staff to work at the facility, appoint such number of staff to work at the facility, and such number of staff if appointed shall be referred to as the authority of the Central Radioactive Waste Management Facility for the purposes of these Regulations. For avoidance of doubts, the Chief Executive Officer of the regulatory body shall be the Registrar of the National Radiation Commission.
(6)The authority of the Central Radioactive Waste Management Facility shall discharge its duties under the instructions given to it by the regulatory body.

6. Functions of the Central Radioactive Waste Management Facility

(1)The Central Radioactive Waste Management Facility shall be the centre for collection and transportation of all radioactive waste from the waste generator's establishments and for treating, conditioning and storing the radioactive waste requiring more than one year decay period to bring down the activity level to below clearance levels.
(2)The Central Radioactive Waste Management Facility shall be responsible for the discharge of exempt waste and to store unconditioned and conditioned radioactive waste until a system for disposal is made available.

7. Responsibilities of the waste generator

(1)The primary responsibility for the safe management of radioactive wastes is imposed on the waste generator who shall take necessary actions to ensure the safety of radioactive waste unless the responsibility has been transferred to another person or organisation as approved by the regulatory body.
(2)The licensee shall make available an interim store for his accumulated radioactive waste in the absence of a Central Radioactive Waste Management Facility, or in case the regulatory body is unable to provide the said facility for such service that store shall serve as his on site interim storage facility.
(3)The waste generator shall have or secure instruments or equipment capable of measuring relevant limits applicable to the waste generated.
(4)The waste generator shall ensure that any released radioactive waste is within specified limits as specified in Table II-1B of the Second Schedule.
(5)The waste generator shall exercise the necessary diligence activities associated with his undertaking or undertakings to minimise the volumes of the radioactive wastes to be produced.
(6)The waste generator shall ensure that he uses as practicably possible the minimum quantities of radioactive materials which are compatible and in accordance with the requirements of his undertaking or undertakings.
(7)The waste generator shall establish working rules and control measures, such as to guarantee that the waste packages to be sent for storage or disposal as radioactive waste, are in accordance with the given information as to activity content, waste form and quality of waste package.
(8)Each waste generator shall appoint a technically competent person with the appropriate independence and authority to be a radioactive materials coordinator or radioactive waste coordinator.

8. Responsibilities of Radioactive Material Co-ordinator

The Radioactive Materials Co-ordinator appointed under paragraph (9) of regulation 7, in addition to assisting persons using radioactive materials in safe and efficient on-site radioactive waste management, shall have the following responsibilities:
(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

(1)No person shall generate or manage radioactive waste without an appropriate licence from the regulatory body.
(2)No person shall dispose of any radioactive waste unless the disposal facility designed and constructed specifically for the purpose is available and licensed.
(3)Proposals from applicants to generate radioactive waste resulting from use of radioactive materials shall specify the following in written application to the regulatory body:
(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.
(4)An applicant shall pay fees prescribed by the regulatory body to cover the cost of the licensing procedures.
(5)The licensee shall comply with all limits and conditions specified in the licence including the amounts and characteristics of waste which may be generated, and stored, and any specific radiation protection and physical security measures.
(6)Any licence issued under paragraph (5) of regulation 9 shall be:
(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 person that proposed to import a sealed source containing radioactive material which ten years after purchase shall have an activity greater than 100MBq shall—
(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

If a modification to an existing practice or source is required by the regulatory body, in order to comply with some requirement of these Regulations, such a requirement shall take effect within such period as may be determined by the regulatory body.

12. Public involvement

The regulatory body shall ensure the public accessibility to facility's programs to improve understanding of waste management issues.

Part III – Waste management operations (regs 13-25)

13. Segregation, collection and characterisation

(1)The generator shall keep control on waste generation to the minimum practicable as provided for under paragraphs (6) and (7) of regulation 7.
(2)The waste generator shall segregate, collect and characterise waste as far as practicable at the point of origin in accordance with the categories specified in regulation 4 in order to facilitate subsequent treatment, conditioning, storage and disposal. Each waste category after segregation shall be kept separately In a suitable container. Sufficient number of containers shall be available where radioactive waste are generated. The waste containers shall—
(a)be easy to handle;
(b)be strong enough to withstand normal handling;
(c)not be affected by the waste content.

14. Container labelling

(1)The licensee shall ensure that each container containing radioactive waste bears a durable, clearly visible label bearing the radiation symbol. The label shall be legible for the whole period of storage and must provide the following information—
(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

(1)A licensee shall ensure that radioactive waste is not to be discharged or released to the environment unless:
(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.
(2)The licensee, before initiating the discharge to the environment of any solid, or gaseous radioactive waste considered to be within discharge limits, shall, as appropriate—
(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.
(3)The licensee, during the operational stages of radioactive waste management, shall—
(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

(1)The waste category prescribed in subparagraph (i) of paragraph (b) of regulation 4 that is expected to decay below clearance levels within one year from its generation, shall be safely stored on-site, and after confirmation by measurements or other means that the clearance levels specified in Table II-1B of Second Schedule have been reached, shall be appropriately discharged or released by the licensee or the authority of Central Radioactive Waste Management Facility.
(2)The licensee may discharge the exempt liquid effluent into sanitary sewer only if the material is readily soluble or is readily dispersible in water.
(3)A licensee may release the exempt sold waste into a waste incinerator or local dump site.
(4)A licensee may discharge exempt gaseous waste into the atmosphere.
(5)Radioactive waste contaminated with toxic compounds or infectious agents which are covered by regulations dealing specifically with these hazardous characteristics, shall be only discharged as per provisions of these Regulations.

17. Release of specific waste

(1)The licensee may release the following materials as if it were not radioactive:
(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.
(2)The licensee may not dispose of tissue under subparagraph (b) of paragraph (1) of regulation 17 in a manner that shall permit its use either as food for humans or as animal feed.

18. Waste storage

(1)The licensee shall arrange and make provisions for interim storage of radioactive waste prior to its clearance or discharge. The interim storage facility shall be properly designed and constructed with at least one physical barrier between the radioactive waste and other material in store. The store shall be large enough to hold all generated and anticipated waste in an orderly manner and keep different categories separated. In addition, the store's design shall provide for:
(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.
(2)The radioactive waste store shall so far as is practicable not contain or be located close to any corrosive, explosive or flammable materials and shall be clearly and legibly marked with the radiation symbol.

19. Preparation for transportation of waste

(1)The authority of the Central Radioactive Waste Management Facility shall be provided with full information on the radioactive waste to be sent to it prior to delivery. If incomplete or incorrect information is given, the Authority of the Central Radioactive Waste Management Facility at the expense of the waste generator, shall make the necessary investigation and shall send a report to the regulatory body for instructions regarding receiving such waste and its further management.
(2)The radioactive waste to be transported to the Central Radioactive Waste Management Facility shall be prepared by the waste generator in accordance with the requirements developed by the Central Radioactive Waste Management Facility as approved by the regulatory body.
(3)The Radioactive Materials Co-ordinator shall supervise the preparation of radioactive waste for the transportation and in particular check that adequate shielding, labelling and documentation is provided.

20. Transportation

(1)Transportation of radioactive waste within the nuclear installation shall be performed by a licensee under separate operating instructions issued by the Management and approved by the regulatory body.
(2)The off-site transportation of radioactive waste shall be in accordance with the relevant national Transport Regulations on hazardous materials and International Atomic Energy Agency Safety Series Nos. 6, 7 and 37 as revised from time to time and as stipulated in other International Atomic Energy Agency Regulations. For international transport, other relevant Regulations and/or agreements shall apply.
(3)Without prejudice to any existing or anticipated law or regulations on the safe transport of radioactive materials in force or which shall come into force at the time these Regulations are in force, the following shall be taken into consideration in relation to the off-site transport of radioactive wastes:
(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.
(4)The regulatory body shall be notified at least fourteen days in advance of any off-site transfer of radioactive waste. The waste generator shall ensure that an acknowledgement receipt of the dispatched radioactive waste is received by him within fourteen days. Any shipment, of which acknowledgement is not received within the specified time, shall be investigated by the sender and a report shall be prepared and submitted to the regulatory body within one week after completion of the investigation but as soon as practicable and not later than twenty-eight days after the date of shipment.

21. Treatment

The Authority of the Central Radioactive Waste Management Facility shall treat the radioactive waste received from the waste generators in order to reduce its volume and to facilitate further conditioning. The treatment method shall be suitably selected for the radioactive waste received depending on such factors as the volume and type of the radioactive waste, the discharge requirements for liquid effluent and additional conditioning requirements.

22. Conditioning

(1)The radioactive waste to be accepted for long term storage, transportation and disposal shall be properly conditioned by the Central Radioactive Waste Management Facility operators.
(2)Waste packages produced by a conditioning process shall be fully characterised with regard to important physical, chemical, radiological, properties specified by the regulatory body.
(3)The waste packages to be transported off-site shall comply with requirements stipulated under section 20(2) and shall meet waste acceptance requirements for disposal.
(4)Radium sources shall be conditioned for storage with regard to the latest internationally accepted technology.

23. Disposal of radioactive waste

Where the radioactive waste does not qualify for discharge or release to the environment or for clearance in a reasonable period of time, it shall be stored in the Central Radioactive Waste Management Facility pending availability of appropriate disposal option.

24. Quality assurance

(1)The licensee shall ensure that all Radioactive Waste Management operations are carried out in accordance with a suitable quality assurance programme commensurate with the scope of activities and approved by the regulatory body. The quality assurance programme shall be planned to ensure that the facilities and equipment are designed, constructed and operated in accordance with specified requirements for safe operation, Regulations and conditions in a licence are complied with, and the radioactive waste packages produced meet the waste package acceptance requirements.
(2)Each licensee shall develop and maintain an accurate and complete documentation system to cover all stages of Radioactive Waste Management from its generation to disposal. The quality assurance programme shall provide for controlled approval, receipt, retention, distribution and disposition of all records important for safety in accordance with the regulatory body's requirements. Records, such as letters, drawings, specifications, etc. must include all pertinent information, such as stamps, initials, and signatures. Each record must be legible throughout the specified retention period.
(3)The licensee shall retain the records until the regulatory body terminates each pertinent licence requiring the record.
(4)The licensee shall maintain adequate safeguards against tampering with and loss of record.
(5)The effectiveness of the quality assurance programme including those of the regulatory body shall be verified by independent audits to ensure that a radioactive waste management programme meets specific requirements, is covered by procedures, and that implementation is adequate.

25. Physical protection

Waste generators and the authority of the Central Radioactive Waste Management Facility shall ensure adequate physical protection measures to prevent any unauthorised access to the radioactive waste management facilities.

Part IV – Reporting to the regulatory body (regs 26-27)

26. Inventory and reporting

(1)The licensee shall prepare and maintain an inventory of existing and anticipated radioactive wastes and submit it to the regulatory body and whenever significant changes in radioactive waste amounts of characteristics occur. The inventory shall be based on the classification system specified in regulation 4, including information on important physical, chemical and radiological characteristics in addition to the quantity of the radioactive waste. The radioactive waste inventory shall be submitted in a form stipulated by the regulatory body.
(2)Each licensee shall report to the regulatory body immediately after its occurrence becomes known to him, and lost, stolen or missing radioactive waste under such circumstances that it appears that an exposure may result to persons in unrestricted areas. Within thirty days after such occurrence, the licensee shall make a written report with a description of the radioactive material involved, its probable disposition, the circumstances under which the loss or theft occurred. and actions that have been taken.
(3)Each licensee shall immediately report to the regulatory body any event involving radioactive waste possessed by the licensee that may have caused or threatens to cause the release of radioactive material, inside or outside of a restricted area, so that the individual could have received an intake in excess of one occupational Annual Limit on Intake.
(4)The Central Radioactive Waste Management Facility shall keep annual records that specify details of quantities and types of—
(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

(1)The licensee shall establish written procedures and have equipment available to:
(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.
(2)The authority of the Central Radioactive Waste Management Facility shall establish written procedures and have equipment available to deal with emergencies involving transport and when requested by the waste generator to advise or assist with any emergency at a waste generator's facility.

Part V – Financing (reg 28)

28. Financial obligation

(1)The waste generator shall secure adequate funds for the management of the radioactive waste.
(2)The waste generator dispatching radioactive waste to the Central Radioactive Waste Management Facility for treatment, conditioning, storage and or disposal services may be charged such fee or fees as determined by the regulatory body.

Part VI – Verification and enforcement (reg 29)

29. Right of entry and inspections

(1)Any person appointed and authenticated by the regulatory body to be the Inspector to control the safety of radioactive waste management may enter at any reasonable time the premises of any licensee, and any other premises where he has reason to suspect that radioactive waste is present, carry out inspections and tests, take samples and photographs, bring in equipment or other experts if he or she has a reason to believe that the radioactive waste may endanger human health or the environment.
(2)The Inspector may recommend to the regulatory body that generates or processes radioactive waste to shut down or stop activities of the waste generator if he believes that the safety is jeopardised.
(3)Each licensee in his premises shall assist the Inspector in his or her duties.

Part VII – Offences and penalties (regs 30-34)

30. Failure to produce a licence

(1)Any person who without reasonable excuse, fails to produce a licence which is required by these Regulations is guilty of an offence.
(2)A person who commits or commit an offence specified under the provision of paragraph (1) of this regulation is liable on conviction to a fine not less than fifty thousand shillings or to imprisonment for a term not less than three years or to both that fine and imprisonment.

31. Obstructions

(1)Any person who wilfully obstructs a radioactive material coordinator or inspector in his duties provided for by these Regulations is guilty of an offence.
(2)A person or persons or organisation who commits or commit an offence specified under the provision of paragraph (1) of this regulation is liable on conviction to a fine not less than forty thousand shillings or to imprisonment for a term of not less than two years or to both such fine and imprisonment.

32. Other offences

Any person or persons who knowingly, wilfully and without any reasonable excuse contravenes, fails or refuses to comply with any other provisions of these Regulations in relation to which contravention, failure or refusal no specific penalty is provided, is guilty of an offence and is liable on conviction to a fine of not less than twenty five thousand shillings or to imprisonment for a term of not less than one year or to both such fine and imprisonment.

33. Offences by body corporate

Any act or omission which is an offence under these Regulations shall if done by a body corporate be deemed to be an offence committed by every Director, Secretary or Manager of the body corporate unless he proves that offence was committed without his knowledge or his consent and that he exercised such diligence to prevent the commission of the offence as he ought to have exercised having regard to the nature of his functions and the circumstances of the case.

34. Appeals

Any person who is aggrieved at the failure of the regulatory body to issue or renew any licence or considers that the regulatory body has revoked or suspended a licence or attached any unreasonable conditions or limits to a licence, may appeal to the Minister and if the Minister is convinced that the person or organisation has been unreasonably treated he may require the regulatory body to take an appropriate defined action.

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 (ALImim) for each radionuclide means the lesser of these values. Each waste generator or the Central Radioactive Waste Management Facility may discharge waste in quantities not exceeding 10ALImim per year.Table II-1B of the Second Schedule gives the numerical values of ALImim for members of the public for the most frequently used radionuclides. The values (waste clearance levels) area the ones to be used in the equations below: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.Ak∑<10 (1)ALImimAk is the activity of radionuclideALImim values are in schedule II Table II-1B for radionuclide k.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 ALImimAk<1. (2)ALImimThe total activity, however, shall not exceed 5MBq per year3. 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 0.1ALImim or 0.05MBq whichever is less per individual dischargeAk<0.1 (3)ALImim[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—

(i) a statement that "this waste package is exempted from nuclear control according to the Radioactive Waste Management Regulations";

(ii) Name and address of sender;

(iii) Signature of sender.]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.A. Occupational minimum annual limits on intake alimim (bq) Of radionuclide by workers based on the 1990 recommendation As given in icrp publication 61 vol 21 no. 4According 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 ALImim)
NuclideBq
H - 3 Water1.00E+09
C - 144.00E+07
F - 184.00+08
Na - 221.00E+07
Na - 245.00E+07
P - 328.00E+06
P - 338.00E+07
S - 351.00E+08
CI - 362.00E+07
CI - 382.00E+08
K - 404.00E+06
K - 425.00E+07
K - 439.00E+07
45 Ca1.00E+07
Ca - 471.00E+07
Cr - 515.00E+08
Mn - 511.00E+07
Mn - 523.00E+08
Mn - 542-00E+07
Mn - 562.00E+07
Fe - 521.00E+07
Fe - 553.00E+07
Fe - 595.00E+06
Co - 563.00E+06
Co - 573.00E+07
Co - 581.00E+07
Co - 602.00E+06
Ni - 632.00E+07
Cu - 642.00E+08
Cu - 675.00E+07
Zn - 622.00E+07
Zn - 654.00E+06
Zn - 69m5.00E+07
Ga - 678.00E+07
Ga - 682.00E+08
As - 732.00E+07
As - 749.00E+06
Se - 759.00E+06
Br - 765.00E+07
Br - 772.00E+08
Br - 824.00E+07
Rb - 81m2.00E+09
Rb - 814.00E+08
Rb - 868.00E+06
Rb - 882.00E+08
Rb - 894.00E+08
Sr - 85m4.00E+09
Sr - 87m7.00E+06
Sr - 904.00E+05
Y - 905.00E+06
Tc - 99m1.00E+09
Tc - 991.00E+09
Mo - 993.00E+07
In - 113m9.00E+08
Sb - 1246.00E+06
I - 1239.00E+07
I - 1251.00E+06
I - 1292.00E+05
I - 1301.00E+07
I - 1318.00E+05
I - 1327.00E+07
Cd - 1091.00E+06
Cd - 1151.00E+07
In - 1115.00E+07
Cs - 1293.00E+08
Cs - 1307.00E+08
Cs - 1313.00E+08
Cs - 1341.00E+06
Cs - 134m1.00E+09
Cs - 1371.00E+06
Ba - 1314.00E+07
Ba - 133m3.00E+07
Ba - 135m4.00E+07
La - 1408.00E+06
Yb - 1691.00E+07
Ir - 1926.00E+06
Au - 1981.00E+07
Hg - 1976.00E+07
Hg - 2032.00E+07
TI - 2013.00E+08
TI - 2043.00E+07
Pb - 2101.00E+04
Pb - 2125.00E+05
Po - 2102.00E+04
Ra - 2269.00E+03
Th - 2329.00E+01
U - 2389.00E+04
Am - 2413.00E+02
Cm - 2445.00E+02
Cf - 2529.00E+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. 4In 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.
NuclideBq
H - 3 Water500,000
C - 1420,000
F - 18200,000
Na - 225,000
Na - 2425,000
P - 324,000
P - 3340,000
S - 3550,000
Cl - 3610,000
Cl - 38100,000
K - 402,000
K - 4225,000
K - 4345,000
Ca - 455,000
Ca - 475,000
Cr - 51250,000
Mn - 515,000
Mn - 52150,000
Mn - 5410,000
Mn - 5610,000
Fe - 525,000
Fe - 5515,000
Fe - 592,500
Co - 561,500
Co - 5715,000
Co - 585,000
Co - 601,000
Ni - 6310,000
Cu - 64100,000
Cu - 6725,000
Zn - 6210,000
Zn - 652,000
Zn - 69m25,000
Ga - 6740,000
Ga - 68100,000
As - 7310,000
As - 744,500
Se - 754,500
Br - 7625,000
Br - 77100,000
Br - 8220,000
Rb - 81m1,000,000
Rb - 81200,000
Rb - 864,000
Rb - 88100,000
Rb - 89200,000
Sr - 85m2,000,000
Sr - 87m20,000
Sr - 903,000
Y - 902,500
Tc - 99m500,000
Tc - 99500,000
Mo - 9915,000
In - 113m450,000
Sb - 1243,000
I - 12345,000
I - 125500
I - 129100
I - 1305,000
I - 131400
I - 13235,000
Cd - 109500
Cd - 1155,000
In - 11125,000
Cs - 129150,000
Cs - 130350,000
Cs - 131150,000
Cs - 134500
Cs - 134rn500,000
Cs - 137500
Ba - 13120,000
Ba - 133m15,000
Ba - 135m20,000
La - 1404,000
Yb - 1695,000
Ir - 1923,000
Au - 1985,000
Hg - 19730,000
Hg - 20310,000
TI - 201150,000
TI - 20415,000
Pb - 2105
Pb - 212250
Po - 21010
Ra - 2264.5
Th - 2320.045
U - 23845
Am - 2410.15
Cm - 2440.25
Cf - 2520.45

Third schedule

A.Principal nuclides used in medicine,Clinical measurements and biological researchAs 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.
RadionuclideHalfLifePrincipalApplicationTypical quantity per applicationWaste types
3H12.26aClinical measurements Biological research LabellingUp to 5 MBqUp to 50 GBqSolid, liquidOrange solvents, Gaseous
14C5950aBiological research labellingLess than 1 GBqUp to 10 MBqSolid, liquidOrange solvents,exhaled CO2
22Na2.6aClinical measurements Biological researchUp to 50 kBqSolid, liquid
24Na15hClinical measurementsUp to 5 GBqLiquid
32P14.3dTherapy Biological researchUp to 200 BqUp to 400 MBqSolid, liquid
35S87.4dClinical measurementsBiological researchUp to 5 GBqSolid, liquid
36CI3.01x105aBiological researchUp to 5 MBqGaseous solid
45Ca47Ca164d4.5dBiological researchClinical measurementsUp to 100 MBqUp to 1 GBqMainly solidsome liquid
51Cr27.7dClinical research Biological researchUp to 5MbqUp to 100 kBgMainly liquid
57Co58Co60Co271.7d60.8d5.26aClinical measurementsCheck sourcesBiological research TherapyUp to 50 kBqUp to 100 TBqSolid, liquidSolid
39Fe44.6dClinical MeasurementBiological researchUp to 50 MBqMainly liquid
99Tm6.0hClinical measurementBiological researchUp to 600 MBqSolid, liquid
57Ga78.26hClinical measurementsUp to 200 MBqLiquid
75Se119.8dClinical measurementsUp to 11 MBqSolid, liquid
85Sr89Sr90Sr64.8d50.5d28.5aClinical measurementsBiological researchTherapyUp to 50 MBqUp to 150 MBqUp to 1500 MBqSolid, liquidSolid
90Y64hTherapyUp to 120 MBqSolid, liquid
103Pd2.8dTherapyUp to 1500 MBqSolid, liquid
111Ln2.8dClinical measurementsBiological researchUp to 500 MBqSolid, liquid
123 I125 I131 I13.2h50d8.04dClinical measurementClinical measurementsBiological researchTherapy LabellingClinical measurementsTherapy Biological researchUp to 800 MBqUp to 500 MBqUp to 500MBqUp to 500 MBqUp to 10GBqUp to 50 MBqSolid, liquidOccasionally vapourSolid, liquidOccasionally vapour
133 Xe5.25dClinical measurementsUp to 200 MBqGaseous
137 Cs30.1aTherapyUp to 500 TBqSolid
201 TI3.02dClinical measurementsUp to 120 MBqSolid, liquid
192 Ir74dSealed source therapyUp to 500 GBqSolid
197 Hg64.4hClinical measurementsUp to 50 MBqSolid, liquid
198 Au2.7dClinical therapyUp to 10 GBqLiquid
241 Am433aClinical measurementsUp to 10 GBqSolid
B.Principal nuclides used in sealed radiation sources In industry and researchAs 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 Principal applicationTypical activity per source
3 H12.3aLight sources, electron capture detectors, targets, electronic valves.From kBq up to 10 TBq
55 Fe2.6aX-ray fluorescenceUp to 5 GBq
57 Co271.7dCalibration sourcesUp to 100 MBq
60 Co5.3aRadiography, irradiatorsUp to 400 PBq
63 Ni100aElectron capture detectorsUp to 50 GBq
85 Kr10.76aThickness gauges, electronic valvesUp to 100 GBq
90 Sr28.1aThickness and density gaugesUp to 10 GBq
134 Cs2.1aDensity gaugesUp to 20 GBq
137 Cs30aRadiography, irradiators, density and level gauges, well-loggingUp to 400 PBq
147 Pm2.62aThickness gauges, light sourcesUp to 2 GBq
169 Yb32dRadiographyUp to 1 TBq
160 Tm128.6dRadiographyUp to 1 TBq
192 Ir74dRadiographyUp to 5 TBq
210 Po138dStatic eliminatorsUp to 20 GBq
238 Pu87.7aX-ray fluorescence analysisUp to 5 GBq
241 Am433aDensity, level and thickness gauges, X-ray fluorescence, well-logging, moisture detectorsUp to 500 GBq
252 Cf2.6aMoisture detectors, neutron sourcesUp to 10 GBq

Fourth Schedule

[Editorial note: The form has not been reproduced.]

Fifth schedule

Application for licence/authorisation to store

[Editorial note: The forms has not been reproduced.]
▲ To the top

History of this document

31 July 2002 this version
Consolidation
17 September 1999
Commenced