FNCA RS-002

FNCA Consolidated Reporton Radiation Safety (Draft)

March 2012
Radiation Safety and Radioactive
Waste Management Group,
Forum for Nuclear Cooperation in
Asia (FNCA)

iCONTENTS
I. Preface ..................................................................................................................................i
II. Framework of Regional Cooperation under FNCA.........................................................ii
III. Status of Radiation Safety in FNCA Member Countries ................................................1
1. Australia.................................................................................................................................. 1
Part 1. Radiation Safety in Radiation Industry Facilities ................................................................. 2
Part 2. Status of Radiation Safety Management ............................................................................. 5
2. Bangladesh............................................................................................................................ 16
Part 1. Radiation Safety in RI Facilities ....................................................................................... 17Part 2. Status of Radiation Safety Management ........................................................................... 21
3. China..................................................................................................................................... 28
Part 1. Radiation Safety in RI Facilities ....................................................................................... 29
Part 2. Status of Radiation Safety Management ........................................................................... 34
4. Indonesia............................................................................................................................... 44
Part 2. Status of Radiation Safety Management ........................................................................... 45
5. Japan..................................................................................................................................... 47
Part 1. Radiation Safety in RI Facilities ....................................................................................... 49
Part 2. Status of Radiation Safety Management ........................................................................... 59
6. Kazakhstan ........................................................................................................................... 83
Part 1. Radiation Safety in RI Facilities ....................................................................................... 84
Part 2. Status of Radiation Safety Management ........................................................................... 88
7. Malaysia................................................................................................................................ 91
Part 1. Use of Radiation Sources and Radiation ........................................................................... 93
Part 2. Status of Radiation Safety Management ......................................................................... 100
8. Mongolia ............................................................................................................................. 108
Part 1. Radiation Safety in Radioisotope Facilities ..................................................................... 109
9. The Philippines ................................................................................................................... 118
Part 1. Radiation Safety in Radioisotope Facilities ..................................................................... 119
Part 2. Radiation Safety in Research Reactors, NPPs and Other Various RI Usage...................... 122
10. Thailand ........................................................................................................................ 11829
Part 1. Radiation Safety in Radioisotope Facilities ..................................................................... 132
Part 2. Status of Radiation Safety Management ......................................................................... 137
11. Vietnam ............................................................................................................................. 146
Part 1. Radiation Safety in Radiation Industry Facilities ............................................................. 147
Part2. Status of Radiation Safety Management .......................................................................... 154

IV. Contributors.................................................................................................................. 158

i

I. Preface
Through the activities of Radiation Safety and Radioactive Waste
Management (RS & RWM) Group in the Forum for Nuclear Cooperation in Asia
(FNCA), we present the book of “The Consolidated Report on Radiation Safety
and Radioactive Waste Management in FNCA Countries”. The purpose of thisreport is a summary of this region based on the mutual understanding on RS &RWM in FNCA countries. The authors believe the reference of this book willcause further improvements of radiation safety and radioactive waste managing
level in FNCA countries.
The authors would like to appreciate the project support by Ministry of
Education, Culture, Sports, Science and Technology (MEXT), Japan.

March 2011.
Project Leader for Japan
Toshiso KOSAKO(The University of Tokyo)iII. Framework of Regional Cooperation under FNCA
1. Introduction of FNCA
The Forum for Nuclear Cooperation in Asia (FNCA) has evolved from the International
Conference for Nuclear Cooperation in Asia (ICNCA) which was established in 1990 with theaim of promoting the application of nuclear technology through collaboration among Asian
countries. During this period the sharing of information, exchanges of scientific personnel andactive cooperative research have been pursued in several fields.
2. Participating Countries
Australia, Bangladesh, China, Indonesia, Japan, Kazakhstan, Korea, Malaysia, Mongolia,
Philippines, Thailand and Viet Nam
3. Goals• To achieve socio-economic development by safe utilization of nuclear technology• To utilize nuclear technology in those fields where it has a distinct advantage• To respond to the needs of the FNCA countries
4. Operational Strategies
1) Framework of Operation
The basic framework of cooperation consists of the following three: Forum meeting
Discussion on cooperation measures and nuclear-energy policies. Forum meeting iscomprised of a ministerial level meeting and a senior official level one.
 Coordinators meeting
Discussion on the introduction, revision and abolishment, adjustment, and evaluation ofcooperation projects by an appointed coordinator from each country.
 Cooperation activities for each project(See the figure on the next page):ii

Figure: FNCA Framework

5. FNCA Radiation Safety and Radioactive Waste Management ProjectThis project superseded Radioactive Waste Management Project and started in 2008 withthe aims of sharing information and experiences in the area of Radiation Safety & Radioactive
Waste Management processes and regulatory issues as well as facilitating safety improvement
and understanding of RS&RWM to public perception in nuclear society.
In each member country, the use of radiation in industry, agriculture, medical treatment, andvarious other fields is rapidly increasing, and at the same time, several countries are looking into
introducing nuclear power plants. In consideration of such tendency, member countries havebeen discussing how to promote the standardization (calibration) on personnel dosimeter,
focusing on appropriate radiation exposure management.
The accumulated results acquired through these activities over ten years were published as aserried of FNCA RWM Consolidated Report on RWM/RS. These reports are available on the
FNCA Website.
[URL: http://www.fnca.mext.go.jp/english/e_project.html]

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III. Status of Radiation Safety in FNCA Member Countries

III. Status of
Radiation Safety in FNCA
Member Countries

FNCA Consolidated Report on Radiation Safety (Australia)

1. Australia
Part 1. Radiation Safety in Radiation Industry Facilities ....................................................... 2
1.1 General ..................................................................................................................... 2
1.1.1 Legislative Framework and Policy for Radiation Safety.............................................. 2
1.1.2 Structure and System (Regulatory organizations) ....................................................... 2
1.2 Outline of Radiation Facilities and Radiation Sources ................................................... 3
1.2.1 Number of Specialists and Workers in Related Organizations...................................... 3
1.2.2 Number of Radiation Facilities including Related Facilities ........................................ 3
1.2.3 Activity and Number of Radiation Sources and Generators ......................................... 4
1.3 Education and Training............................................................................................... 5
1.3.1 Radiation Industry Usage ......................................................................................... 5
1.3.2 Radiological Protection............................................................................................ 5
1.4 Standardization on Radiation and Radioactivity ............................................................ 5
Part 2. Status of Radiation Safety Management ................................................................... 5
2.1 Radiation Safety Management in various Radiation Industries ....................................... 5
2.1.1 Radiation Safety Management System ...................................................................... 5
2.1.2 Radiological Protection for Radiation Workers........................................................... 6
2.1.3 Radiological Protection for Radiation Area ................................................................ 7
2.1.4 Radiological Protection for the Public ....................................................................... 8
2.1.5 Radiation Emergency Preparedness .......................................................................... 8
2.2 Radiation Safety Management in Research Reactors ..................................................... 9
2.2.1 Radiation Safety Management System ...................................................................... 9
2.2.2 Radiological Protection for Radiation Workers........................................................... 9
2.2.3 Radiological Protection for Radiation Area .............................................................. 10
2.2.4 Radiological Protection for the Public ..................................................................... 10
2.2.5 Radiation Emergency Preparedness ........................................................................ 11
2.3 Radiation Safety Management in Nuclear Power Plant................................................ 122.3.1 Radiation Safety Management System .................................................................... 13
2.3.2 Radiological Protection for Radiation Workers......................................................... 14
2.3.3 Radiological Protection for Radiation Area .............................................................. 14
2.3.4 Radiological Protection for the Public ..................................................................... 14
2.3.5 Radiation Emergency Preparedness ........................................................................ 15

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FNCA Consolidated Report on Radiation Safety (Australia)

1. Australia
Part 1. Radiation Safety in Radiation Industry Facilities
1.1 General
1.1.1 Legislative Framework and Policy for Radiation Safety
There are nine jurisdictions for radiation protection in Australia - the federal government, six
States, and two Territories. Radiation Safety legislation is implemented within each jurisdiction inAustralia and is in compliance with the IAEA BSS and IAEA GS-R-1. A committee comprised ofCommonwealth and State representatives ensures national coordination between jurisdictions.
1.1.2 Structure and System (Regulatory organizations)
Australia has a federal system of government, and the regulation of radiation safety andradioactive waste management and disposal comes under both Commonwealth (federal) andState/Territory regulation. The States and Territories are responsible for regulating the use,
manufacture, transport and disposal of radioactive materials under their control or the control ofprivate companies or individuals in accordance with State and Territory Acts and Regulations.
These Acts and Regulations are administered by State or Territory radiation safety authorities suchas the environmental protection authorities and health departments in each state.
Table 1: Legislative jurisdictions, Regulators and Regulations
Jurisdiction
Regulator
Acts/Regulations
New South Wales
DepartmentofEnvironment, Radiation Control Act 1990, Radiation Control
Climate Change and Water
Regulation 2003
Australian
Capital ACT HealthSame as Federal government
Territory
Victoria
Department of Health
Radiation Act 2005, Radiation Regulations 2007
Tasmania
Dept of Health and Human Radiation Protection Act 2005 and Radiation
Services
Protection Regulations 2006
South Australia
Environment Protection Authority
Radiation Protection and Control Act 1982,
Radiation Protection Control (Ionising Radiation)
Regulations 2000, Radiation Protection andControl (Transport of Radioactive Substances)
Regulations 2003
Western Australia
Radiological Council
Radiation Safety Act 1975-1999, Radiation
Safety (General) Regulations 1983-2003,
Radiation Safety (Qualifications) Regulations
1980-2000, Radiation Safety (Transport ofRadioactive Substances) Regulations 2002
Queensland
Queensland Health
Radiation Safety Act 1999, Radiation Safety
Regulation 1999.
Northern Territory
Department of Health and Families Radiation Protection Act 2009, Radiation
Protection Regulations 2009.
Federal government
Australian Radiation Protection Australian Radiation Protection and Nuclear
and Nuclear Safety Agency
Safety Act No. 133, 1998, Australian Radiation
Protection and Nuclear Safety Regulations
1999.

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FNCA Consolidated Report on Radiation Safety (Australia)

Similarly, the Commonwealth Government is responsible for managing radioactive material inorganisations under its control, including Departments, Agencies, Bodies Corporate andcontractors. All activities undertaken by these organisations with respect to radiation (including
nuclear activities, dealings, handling radioactive materials or transport) are regulated by theAustralian Radiation Protection and Nuclear Safety Agency (ARPANSA), which is funded bygovernment as part of the Health and Ageing Portfolio. This includes regulating the managementof nuclear activities and storage of radioactive waste at Commonwealth agencies such as theAustralian Nuclear Science and Technology Organisation (ANSTO), the Commonwealth Science
Industry and Research Organisation (CSIRO) and the Department of Defence.
ARPANSA is also tasked with promoting uniformity of radiation protection and nuclear safety
policy and practices across all jurisdictions (Commonwealth, the States and the Territories). In
addition to the Acts and Regulations listed in the table above, a series of codes and standards onradiation protection have been issued by ARPANSA as the Radiation Protection Series andprovide guidelines for handling, processing and disposal of radioactive materials and waste. These
codes and standards are issued following Commonwealth/State consultation and public comment.
As part of ARPANSA’s Radiation Protection Series, A National Directory for Radiation
Protection was established to provide an agreed framework for radiation safety, including both
ionizing and non-ionizing radiation, together with clear regulatory statements to be adopted by the
Commonwealth, States and Territories. The regulatory elements of the Directory are adopted andenforced by each jurisdiction using existing Commonwealth/State/Territory regulatory frameworks.
The first edition of the directory was published in 2004 and an amended version released in 2010 for
adoption by the States and Territories.
1.2 Outline of Radiation Facilities and Radiation Sources
1.2.1 Number of Specialists and Workers in Related Organizations
The number of people working with radiation related industry in Australia is difficult tocorrectly define however a number is available and is referenced in the Australian Radiation
Protection And Nuclear Safety Agency (ARPANSA) Technical Report 139, “Personal Radiation
Monitoring Service and Assessment of Doses Received by Radiation Workers (2004)”.
ARPANSA provides a Personal Radiation Monitoring Service that enables radiation workers tomonitor the radiation dose received in their occupations. Currently the Service monitors
approximately 35,000 workers and maintains dose histories for over 115,000 people.
Refer to date from Tables 3, 4 &5 of TR 139.
1.2.2 Number of Radiation Facilities including Related Facilities
There are a number of small commercial and state run operators of radiation facilities
associated chiefly with medical treatment. These include eight cyclotron facilities in operation inAustralia: three in Melbourne, two in Sydney, one in Perth and two in Brisbane. There are around
100 linear particle accelerators Australia wide which are located in cancer treatment facilities.
There are also 2 commercial facilities for the irradiation of food which are located in NSW andVictoria.
The largest radiation facilities are run by the Australian government. These include:- OPAL, a 20 MW open pool light water research reactor and associated neutron scattering
facilities at ANSTO. ANSTO produces radioisotopes for medical and commercial use
from reactor operations and also operates the Gamma Technology Research Irradiator.

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FNCA Consolidated Report on Radiation Safety (Australia)-

The Australian Synchrotron, a 3 GeV radiation facility built in Melbourne, Victoria

1.2.3 Activity and Number of Radiation Sources and Generators
Sources are registered with the relevant regulators in each state and territory however there are
no inventories for these in each jurisdiction. ANSTO maintains inventories of its radioactive
sources which are licensed by ARPANSA.
Large inventories of disused radioactive sources exist in many countries that have no other nuclear
activities and therefore represent the only radioactive waste that needs to be managed safely. The
absence of nuclear activities may also contribute to the risk associated with the management of
disused radioactive sources since these countries often lack the necessary infrastructure and technicalpersonnel required for the safe management of radioactive waste. Whilst Australia does not lack thenecessary infrastructure to manage its disused sources the absence of a centralised storage or disposal
facility for such radioactive sources provides for a level of concern and uncertainty.
In Australia the main source and generation of spent and disused sources is in medical applications
by hospitals and medical facilities typically for teletherapy and brachytherapy applications. Most of theold radium sources used in brachytherapy have been replaced by Co-60, Cs-137 and Ir-192. Co-60 is
the most common radionuclide used in teletherapy, although some Cs-137 sources are also in use.
Gamma radiation is used to treat approximately half of all cancer patients with solid tumours. Cobalt
and caesium teletherapy sources are among the higher activity sources in general use.
Radioactive sources are also used in education and research and contain a wide variety ofradionuclides including Co-60, Cs-136 and Am-241. Industrial applications typically use I-131 forNon-destructive imaging of pipe welds. Co-60 and Cs-137 sources are also used for industrial
radiography. Large neutron and gamma sources are used in mining, as well as in oil and gas welllogging. The most common industrial radioactive sources are used in level and thickness gauges and inprocess control. If these gauges are not removed when a facility is closed, they can end up in metal
recycling facilities.
ARPANSA’s Radiation Health & Safety Council is looking into Australia’s need to establish
a process that ensures the integrity and security of a source database, security checks, and threat ofdiversion of radioactive material. ANSTO is coordinating and funding the S-E Asia Regional Securityof Radioactive Sources Project to address awareness of poorly controlled or vulnerable radioactive
sources in S-E Asia and the Pacific, a lack of border controls, detection capability and regulation. The
aim of the ANSTO project was to prevent acquisition of sources by unauthorised persons, and prevent
serious accidents from uncontrolled sources. The four objectives were to strengthen regulatory andlegislative controls, apply standards and train regulators, develop capabilities in equipment and provide
training in its operation, and to identify and address situations involving vulnerable or orphan
radioactive sources. Outcomes of the project so far included regulations developed and being
implemented in Indonesia, Philippines and Vietnam, with progress in Malaysia and Thailand. Radiation
detection equipment provided (with US NNSA) to Indonesia, Philippines, Vietnam, Thailand andCambodia, including training. Capacity building has included running over 20 workshops for 430
participants from 11 countries. Source management activities have included identifying and managing
orphan sources in Cambodia and PNG, assessing storage of disused sources in Indonesia, Philippines,
Vietnam and Thailand, and giving advice on disused sources in Fiji, Vietnam and Cambodia.

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FNCA Consolidated Report on Radiation Safety (Australia)

1.3 Education and Training
1.3.1 Radiation Industry Usage
The ARPANSA National Directory for Radiation Protection requires that all occupations andprofessions who use radiation sources meet the relevant professional competency requirements. In
most cases, competency is evidenced by formal qualification in their field and radiation safety
training is incorporated in the overall curriculum. Health related occupations include medical
practitioners, dental practitioners, veterinary surgeons, diagnostic radiographers, radiation
therapists, nuclear medicine technologists, health and medical physicists and chiropractors.
Industry related occupations include industrial radiographers, borehole loggers, radiation source
testers and persons servicing, installing, commissioning, maintaining, repairing or manufacturing
radiation sources. The evidence of qualification required for each of these occupations is listed in
Schedule 6 – Competency Requirements for Authorisation to Use Radiation Sources for Specified
Practices (ARPANSA National Directory for Radiation Protection).
1.3.2 Radiological Protection
Education and training in radiation safety and radiological protection is provided by numerous
companies, health departments and institutions within Australia with formal training courses
undergoing approval by ARPANSA. There are around fifty providers of around 100 radiation
safety training courses covering subjects including general radiation awareness, radiation
protection, use of radionuclides, use of gauges, transport, and use of radiation in medical
procedures.
1.4 Standardization on Radiation and Radioactivity
Training courses are developed according to the jurisdictional regulations and as such there
may be some different recommendations and exemption criteria (some are based on total activity
and others are on activity concentration). However, the approaches to radiation protection shouldbe generally consistent and the dose limits in line with those stated in the National Directory for
Radiation Protection (see Table 2).

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Management in various Radiation Industries
2.1.1 Radiation Safety Management System
The management of radiation safety within various radiation industries is governed by thejurisdictional regulator according to their regulations, standards and codes. Federally, themanagement of radiation safety is governed by the specific standards, codes and guides in the
Radiation Protection Series (RPS) published by ARPANSA.
These encompass all radiation management considerations for research, industrial and medical
related facilities as follows:- Limiting exposure to ionizing radiation and national standard for limiting occupational
exposure to ionizing radiation (RPS 1)- Code of practice and safety guide for the safe transport of radioactive material (RPS 2 &2.1)

5FNCA Consolidated Report on Radiation Safety (Australia)--

Recommendations for the discharge of patients undergoing treatment with radioactive
substances (RPS 4)
Code of practice and safety guide for portable gauges containing radioactive sources(RPS 5)National Directory for Radiation Protection, December 2009 (RPS 6)
Recommendations for intervention in emergency situations involving radiation exposure(RPS 7)
Code of practice for exposure of humans to ionizing radiation for research (RPS 8)
Code of practice and safety guide for radiation protection and radioactive waste
management in mining and mineral processing (RPS 9)
Code of practice and safety guide for radiation protection in dentistry (RPS 10)
Code of practice for the security of radioactive sources (RPS 11)
Code of practice and safety guide for safe use of fixed radiation gauges (RPS 13)
Code of practice for radiation protection in the medical applications of ionizing radiation(RPS 14) and safety guides for radiation protection in diagnostic and interventional
radiology, nuclear medicine and radiotherapy (RPS 14.1, 14.2 and 14.3)
Safety guide for the management of naturally occurring radioactive material (NORM)(RPS 15)
Safety guide for the predisposal management of radioactive waste (RPS 16)
Code of practice and safety guide for radiation protection in veterinary medicine (RPS 17)
Code of practice for radiation protection in the application of ionizing radiation bychiropractors (RPS 19)

2.1.2 Radiological Protection for Radiation Workers
An increase in a person’s exposure to ionizing radiation, even at low doses, is assumed to increase
the risk of harm to that person’s health. As such, all radiation industries and facilities are required to
implement a system of radiation protection which limits possible detrimental effects arising fromoccupational radiation exposure. This ALARA approach involves the design of processes in such a way
as to minimise exposure and to ensure that occupational dose limits are met. Radiological protection isachieved through the following hierarchy:- avoidance of exposure, where practicable;- isolation of sources of radiation, where practicable, through shielding,- containment and remote handling techniques;- engineering controls, such as local exhaust ventilation to remove contaminants from the workplaceenvironment;- adoption of safe work practices, including work methods which make appropriate use of time,
distance and shielding to minimise exposure; and- where other means of controlling exposure are not practicable, the use of approved personal
protective equipment.
ARPANSA has derived dose limits for ionizing radiation to be adopted nationwide as follows:

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FNCA Consolidated Report on Radiation Safety (Australia)

Table 2: Radiation Dose Limits

Dose limit1
Application
Effective dose
Annual equivalent dose in
the lens of the eye
the skin5
the hands and feetOccupational
Public20 mSv per year, averaged 1 mSv in a year4
over a period of 5consecutive calendar years2,3
150 mSv
500 mSv
500 mSv

15 mSv
50 mSv-

1 The limits shall apply to the sum of the relevant doses from external exposure in the specified period and the 50-year
committed dose (to age 70 years for children) from intakes in the same period.
2 With the further provision that the effective dose shall not exceed 50 mSv in any single year. In addition, when apregnancy is declared by a female employee, the embryo or foetus should be afforded the same level of protection as
required for members of the public.
3 When, in exceptional circumstances*, a temporary change in the dose limitation requirements is approved by theappropriate authority, one only of the following conditions shall apply: (a) the effective dose limit shall not exceed 50
mSv per year for the period, which shall not exceed 5 years, for which the temporary change is approved, or (b) the
period for which the 20 mSv per year average applies shall not exceed 10 consecutive years and the effective dose shallnot exceed 50 mSv in any single year.
4 In special circumstances, a higher value of effective dose could be allowed in a single year, provided that the averageover 5 years does not exceed 1 mSv per year.
5 The equivalent dose limit for the skin applies to the dose averaged over any 1 cm2 area of skin, regardless of the total
area exposed.

Regulatory requirements are in place in all jurisdictions for controlling exposure to medical
personnel. These are implemented by a well qualified workforce of medical and hospitalphysicists who interact well with each other through professional bodies.
Doses to radiation workers are measured either through thermoluminescent dosimeters or electronic
personal dosimeters. ARPANSA provides a national
dosimetry service for some 35,000 radiation workers nationally on a cost recovery basis.
Australian Nuclear Science and Technology Organisation (ANSTO) provides an in-house service
for 850 radiation workers and Queensland Health provides a dosimetry service for some 5,000
Queensland radiation workers. A variety of other commercial personal dosimetry service
providers cater for an estimated 9,000 other radiation workers. Calibrations of dosimeters throughservice providers are traceable to national standards. ARPANSA and ANSTO dosimetry services
participated in the IAEA/RCA intercomparisons held under IAEA/RCA RAS/9/029.
Australia does not have a national register for occupational exposures and there are no current
plans to establish one. Dose records are held by the operator and the dosimetry service provider
and this data is reviewed by the relevant regulator. Individual monitoring for intakes ofradionuclides is available from ANSTO and ARPANSA (for whole body monitoring andbioassay).
2.1.3 Radiological Protection for Radiation Area
Monitoring of workplace areas is required to be performed by the operator with regulatory
inspectors having the capacity to check this. Commercial consulting services are also available tocarry out such monitoring for operators who do not have the required in-house expertise.
Radiological protection measures for specific radiation areas are implemented by the operators inorder to comply with the relevant regulations.

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FNCA Consolidated Report on Radiation Safety (Australia)

Through their Radiation Health and Safety Advisory Council, ARPANSA have also identified
the need to assess the radiation levels in workplaces not normally associated with radiation
activities and to provide technical support. These include potential radiation exposure from:- Residue Naturally Occurring Radioactive Minerals from historic mineral sands operations.
- Radioactive scale from off-shore oil and gas.
- Mineral processing activities where radiation levels are higher than background.
- Orphan sources which are discovered within the recycling industry.
- Elevated radon levels from decay of naturally occurring radioactive minerals
2.1.4 Radiological Protection for the PublicRadiological protection measures are implemented by the states, territories and federal
government for members of the public as an inherent part of applying their regulations regarding
general radiation safety. Dose limits for the public are to comply with those specified in
ARPANSA’s National Directory for Radiation Protection (see Table 2).
ARPANSA have carried out characterisation studies within Australia of radon and natural
background to determine expected doses to the public. ARPANSA also assesses radiation doses to
the Australian population from medical radiation practices through national surveys. Advice isprovided to medical professionals, patients and the public on medical exposures and risks.
Additionally, ARPANSA conducts a quality assurance test program to monitor the quality ofradiopharmaceuticals and undertakes for the Therapeutic Goods Association (TGA) the evaluationof the chemistry, manufacture, quality control and radiation dosimetry aspects of new drug
applications and variations to conditions of TGA registration.
The capability to monitor foodstuffs for radioactivity is available within Australia for specificpotential threat situations. ARPANSA, as part of the Commonwealth Department of Health, is thenational competent authority for dealing with such threats, for doing check monitoring and issuing
guidance advice to all stakeholders.
2.1.5 Radiation Emergency Preparedness
The following organisations are responsible for managing and planning the response to
emergencies that may involve radiation:- National Warning Point – Attorney Generals Department Coordination Centre (AGDCC),
24h/d- National Competent Authority - Australian Radiation Protection and Nuclear Safety Agency(ARPANSA) - on call
- Emergency Management Australia (EMA, part of the AGDCC) 24h/d- Bureau of Meteorology - on call
- State and Federal Police (Victoria, New South Wales, Queensland, Northern Territory, South
Australia, Western Australia, Australian Capital Territory, Tasmania, Commonwealth)- State and Federal Combat Agencies (Fire, Ambulance, State Emergency Services etc.,)- Australian Defence Force (ADF)
The following plans are in place in the event of a radiological emergency:- Nuclear Powered Warship accident (OPSMAN1)- Port Safety Plans/Visiting Ships Operations Orders- Space debris re-entry (COMDISPLAN SPRED)- Accident/misuse of Radioactive/Nuclear material and Radiological/Nuclear Terrorism

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FNCA Consolidated Report on Radiation Safety (Australia)(COMDISPLAN)- International Response under Convention for Requesting Assistance
2.2 Radiation Safety Management in Research Reactors
2.2.1 Radiation Safety Management System
Australia’s only nuclear reactor (OPAL) is operated by the Australian Nuclear Science andTechnology Organisation and is funded by the federal government. As such, ANSTO is regulatedby ARPANSA and its safety management system must comply with their requirements. ANSTO is
dedicated to implementing international best practice in this area and adopts the relevant
recommendations given by the IAEA. ANSTO has adopted an ALARA approach to radiation
exposure and have implemented a more stringent internal occupational dose limit of 15 mSv incomparison with the IAEA and ARPANSA limit of 20 mSv per year effective dose.
2.2.2 Radiological Protection for Radiation Workers
ANSTO designs and operates all processes involving radioactivity with the aim of keeping
doses ALARA and within their internal dose constraint of 15 mSv per year effective dose.
Radiation protection controls are implemented according to the hierarchy described in section 1.2.
Processes involving radiation include radioisotope production, research, radioactive waste
management and storage of radioactive materials. Dose rates are monitored both through use ofarea radiation monitors and through personal dosimetry. Health Physics Surveyors are employed
to provide radiological advice to personnel, to give on the job monitoring during tasks and toassess the radiological status of work areas. Radioisotope production areas, reactor operations
and waste management have on-call access to health physics support with some operations unable
to be carried out without a health physics surveyor in attendance.
ANSTO provides an in house dosimetry service for 850 radiation workers which involves awhole body monitoring program for internal dose and external dose measurement using
thermoluminescent detectors. Whole body monitoring (internal dose monitoring) is carried out
three to four times a year for reactor operators, radioisotope production staff, radioisotope delivery
drivers, handlers of nuclear fuel and waste management staff. External dosimetry data collectedfrom thermoluminescent detectors is reviewed on a monthly basis by ANSTO’s personal
dosimetry service. Any anomalous or unusually high levels of effective dose are investigated todetermine the cause of exposure. Through this process of review and investigation, improvements
to practices and equipment are identified and implemented in order to prevent continued or
potential abnormal high exposure. Radiation workers at ANSTO are also equipped with electronic
personal dosimeters which are used to measure their cumulative dose during a certain task or overthe course of the day and help them to manage their dose exposure. Urine sampling is carried out
for personnel during specific operational campaigns involving exposure to tritium. Thyroid
monitoring and urine sampling is carried out for personnel who are involved in the production of
Iodine-131.
Radiation workers are equipped with the personal protective equipment (PPE) required for theparticular work area (depending on its radiation classification) and for specific tasks. In classified
radiation areas compulsory PPE include overshoes, overcoats, and safety shoes. For tasks
involving radioactive contamination the PPE required may include gloves, disposable overalls,
safety glasses, face shields, full face masks with filters and full suits with breathing air.

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FNCA Consolidated Report on Radiation Safety (Australia)

2.2.3 Radiological Protection for Radiation Area
Work processes and areas are designed to keep radiation exposure to a minimum. Where thepotential for exposure to radiation or contamination still exists, shielding and mechanical ventilation are
employed to minimise the dose received. Areas are classified according to the potential radiation andcontamination level.
Table 3: Classification Levels for Radiation and Contamination Areas
RadiologicalArea Potential
Radiation Removable
SurfaceColour CodeExposure
Levels Contamination Levels(individual,
effective (averaged over 2000 h
mSv per year)
per year)RED
6 to 20
0.3 to 1 DL
BLUE
1 to 60.05 to 0.3 DL
WHITE<1< 0.05 DL

Airborne
Potential
Contamination Levels(averaged over 2000 h
per year)
0.3 to 1 DAC
0.05 to 0.3 DAC<0.05 DAC

Table 4: Maximum Permitted Activity in Contamination Areas in Terms of Annual Limits on Intake (ALIs)

Location
Red Contamination Area
Open Room
Fume Cupboard
Glove-box
Blue Contamination Area
Open Room
Fume Cupboard
Glove-box
White Contamination Area
Open RoomNature of Operation
Volatile or dry Slightly volatile or Non-volatileand dusty
dry, non-dusty
operations
10-3 ALI
102 ALI
104 ALI

10-1 ALI
103 ALI
105 ALI

101 ALI
104 ALI
106 ALI

10-4 ALI
101 ALI
103 ALI
Not Permitted

10-2 ALI
102 ALI
104 ALI
Not Permitted

1 ALI
103 ALI
105 ALI
0.1 ALI

wet

Local area radiation monitors are used within all ‘Red’ classified work areas and ‘Blue’ areas where
higher than background radiation levels are to be expected. These monitors are configured to raise an
alarm when an upper radiation set point has been reached to alert personnel to discontinue the process,make safe or evacuate. Red and Blue contamination classified work areas are also equipped withcontamination detectors for checking personnel on exiting the area. All contamination and radiation
monitors are calibrated annually by ANSTO’s calibration services.
Dose and contamination surveys are carried out by health physics surveyors as scheduled and also
at request. Items that are transferred from a Red or Blue classified area (radiation and/or contamination)
to another building are monitored by health physics and a clearance certificate issued to advise thereceiver of the item’s dose, contamination level and any special handling requirements.
2.2.4 Radiological Protection for the Public
Through the safety assessment process (Safety analysis reports for facilities and safety
approval submissions for new and ongoing processes) ANSTO addresses any radiological issues
that may have an impact on the public. As such, processes and modifications are only allowed
once the operator can prove the safety of their process/facility from the perspective of design, useof equipment, maintenance, operational and administrative controls in place.

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FNCA Consolidated Report on Radiation Safety (Australia)

The main ways in which members of the general public may be exposed to radiation isthrough:- potential release of radionuclides into the environment from atmospheric discharges fromstacks (tritium, volatile fission products, activation products and noble gases released fromisotope production facilities, research laboratories and waste management areas)- Discharge of low level liquid effluent via the Sydney Water Corporation sewer to the ocean.
- Radionuclide transport by surface/ground water and/or contaminated airborne particulate
dispersion from buried waste in a small low level radioactive waste disposal site
Stack monitoring for radionuclides is carried out continually to determine compliance with thelimits imposed by the regulator and to fulfil the duty to protect members of the public. A programof environmental sampling of air, ground water and sediments at various locations around the
ANSTO site has been carried out for more than a decade and consistently demonstrates that
ANSTO’s activities have no impact on public radiological safety or the environment.
Radioactivity discharge limits are set for liquid effluent to meet the WHO Guidelines for Drinking
Water Quality (2004) for radioactive species at the point of the receiving sewage treatment plant(Cronulla). Waste water is analysed for gross alpha and beta radioactivity concentration and mustcomply with the derived limits (based on a dilution factor of 25 prior to the sewage plant) before it
is released. Annual sampling at the sewage treatment plant and outfall has always shown that thelevels of radioactivity detected are below those set in the WHO guidelines. The informationcollected from environmental monitoring is published annually and made available to the public
and the regulator (ARPANSA).
2.2.5 Radiation Emergency Preparedness
ANSTO has Emergency Planning arrangements in place to enable effective management andresponse in the event of a radiation emergency. The five main components to the emergency planningarrangements include:- Response plans- Standing Operating Procedures (SOPs)- Communication and consultation- Testing and review- Emergency response training
The response plan was developed by ANSTO’s Quality, Safety, Environment and Radiation
Protection section (QSERP) and is practised once every two years to ensure all participants are familiar
with its contents, to test specific aspects and practise procedures associated with the plan.
ANSTO provides specific emergency response training to ANSTO’s emergency response staff
and includes regular workplace exercises focusing on various emergency procedures and response.
The objective of these exercises is to continually improve ANSTO’s emergency arrangements andto identify further emergency response training needs.
There are a number in plans in place which would come into effect in the event of aradiation emergency where there may be possible off-site consequences:-

Sutherland Shire Local Disaster Plan
The Georges River District Disaster Plan
NSW State Hazardous Emergency Sub-Plan

11

FNCA Consolidated Report on Radiation Safety (Australia)-

NSW State Disaster Plan, etc.
(ERNET/ENATOM/RANET)

In such an event ANSTO would continue to provide technical advice and assistance to the
NSW authorities that would be in control.
2.3 Radiation Safety Management in Nuclear Power Plant
Radioactive waste in Australia is generated by research, industry, medical applications,research reactor operation and radiopharmaceutical production. Naturally occurring radionuclides(NORM) and technologically enhanced naturally occurring radioactive materials (TENORM) areproduced in Australia by the mining, mineral sands processing and other resources sectors.
Australia has no nuclear power plants.
Australia has a number of radioactive waste management facilities where radioactive wastes
are held in storage and/or processed. The largest waste management facility is run by ANSTO for
the processing of wastes arising from activities associated with its nuclear research reactor. Other
small waste stores and processing facilities are managed by the Department of Defence and State
governments (comprising of waste arising mostly from public hospitals). Radioactive waste
management facilities in Australia range from custom built decontamination facilities andradioactive waste stores, such as those at ANSTO, to temporary storage facilities whereradioactive material is held in transit. Current operational radioactive waste management facilities
in Australia are listed in Table 3.2.
Table 3.2: Radioactive Waste Management Facilities

Location

Main Purpose

ANSTO,Heights, NSW

Lucas Treatment and Packaging

ANSTO
Heights, NSW

Lucas Storage

Mt
WaltonEast
Intractable
Waste
Facility, WA
WoomeraProtected
Area, SA
WoomeraProtected
Area, SAEsk Storage Facility,
Qld
OthersEssential Features and estimated waste
inventory
Management of waste from research reactor
operation, radiopharmaceutical production,
research and development
1620 m3 low level waste
417 m3 intermediate level waste
Near surface disposal of low level radioactive
waste generated in the State of Western Australia

Disposal

Storage

Storage of low level and intermediate level waste
owned by Department of Defence
Storage of 2010 m3 contaminated soil owned by
CSIRO
Storage of radioactive waste (sources and low
volume material) generated in the State ofQueensland.
Over 100 locations around the country where lowlevel, short-lived and/or long-lived intermediatelevel radioactive waste is stored

Storage
Storage

Storage

Australia is in the process of developing and implementing a National Waste Management Facility(NWMF) to safely manage radioactive wastes generated in Australia. On 25 February 2010 the
Senate referred the National Radioactive Waste Management Bill 2010 for inquiry and report. The
purpose of the Bill is to repeal the Commonwealth Radioactive Waste Management Act 2005 and to

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FNCA Consolidated Report on Radiation Safety (Australia)

substitute a new process to select and establish a facility for managing, at a single site, radioactive waste
arising from medical, industrial and research uses of radioactive material in Australia.
It is internationally accepted that centralised radioactive waste management facilities offer
substantial safety and security benefits by minimising risk of accidental loss of control of radioactive
waste, thereby protecting the community and environment from any adverse effects. The AustralianGovernment has introduced legislation to repeal the Commonwealth Radioactive Waste Management
Act 2005 and introduce the National Radioactive Waste Management Bill 2010 (Bill). The newlegislation will restore procedural fairness rights for establishing a purpose built radioactive waste
management facility.
The Bill will establish a facility to manage radioactive waste generated by Australia’s medical,
industrial, agricultural and research use of nuclear material and will ensure that the selected site
undergoes full environmental, heritage and other approval processes. Currently Australia’s radioactive
waste is stored at more than 100 less than ideal sites around Australia. This approach will promote theconsistent, safe and responsible management of radioactive waste, in accordance with Australia’s
obligations as a party to the Joint Convention on the Safety of Spent Fuel Management and on the Safetyof Radioactive Waste Management.
The three sites selected by the previous Government on Defence land in the Northern Territory havebeen ruled out and there will be no pre-determined site outcome – the new Bill requires any site to be
volunteered by landowners. In February 2009, Parsons Brinckerhoff finalised a series reports, on the
preliminary site characterisation investigations for a radioactive waste management facility on
previously identified sites in the Northern Territory.
2.3.1 Radiation Safety Management System
The radiation safety management system for handling wastes and managing waste processing
operations would generally be covered within the facility radiation safety management system.
There are however some additional considerations in relation to the classification of radioactive
wastes based on their physical form, chemical nature and radioactivity. These waste
classifications provide guidance as to what radiation safety measures are required for bothprocessing and storage.
In April 2010, ARPANSA issued a Safety Guide on the Classification of Radioactive (RPS 20)
waste to be adopted nationally in order to standardise the classification of radioactive waste withreference to the IAEA General Safety Guide, Classification of Radioactive Waste (No. GSG-1).
Six classes of waste have been derived as the basis for the classification scheme:
 Exempt waste (EW): Waste that meets the criteria for exemption from regulatory control forradiation protection purposes. Exemption activity concentrations and exempt activities ofradionuclides are specified in Schedule 6 of the NDRP (ARPANSA 2010).
 Very short lived waste (VSLW): Waste that can be stored for decay over a limited period of
up to a few years and subsequently exempted from regulatory control according toarrangements approved by the relevant regulatory authority, for uncontrolled disposal, use ordischarge. This class includes waste containing primarily radionuclides with very shorthalf-lives often used for industrial, medical and research purposes.
 Very low level waste (VLLW): Waste that does not meet the criteria of EW, but does need amoderate level of containment and isolation and therefore is suitable for disposal in a near

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FNCA Consolidated Report on Radiation Safety (Australia)

surface, industrial or commercial, landfill type facility with limited regulatory control. Suchlandfill type facilities may also contain other hazardous waste. Typical waste in this classincludes soil and rubble with low activity concentration levels. Concentrations of longer-lived
radionuclides in VLLW are generally very limited.
 Low level waste (LLW): Waste that is above exemption levels, but with limited amounts oflong lived radionuclides. Such waste requires robust isolation and containment for periods of
up to a few hundred years and is suitable for disposal in engineered near surface facilities.
This class covers a very broad range of waste. Low level waste may include short lived
radionuclides at higher activity concentration levels and long lived radionuclides, but only at
relatively low activity concentration.
 Intermediate level waste (ILW): Waste that, because of its content, particularly of long lived
radionuclides, requires a greater degree of containment and isolation than that provided bynear surface disposal. However, ILW needs little or no provision for heat dissipation during
its storage and disposal. Intermediate level waste may contain long lived radionuclides, inparticular alpha emitting radionuclides, which will not decay to an activity concentration
acceptable for near surface disposal during the time for which institutional controls can berelied upon. Therefore waste in this class requires disposal at greater depths, in the order oftens of metres to a few hundred metres.
 High level waste (HLW): Waste with activity concentration levels high enough to generatesignificant quantities of heat by the radioactive decay process or waste with large amounts oflong lived radionuclides that need to be considered in the design of a disposal facility for such
waste. Disposal in deep, stable geological formations usually several hundred metres or more
below the surface is the generally recognised option for disposal of HLW.
For operational purposes, ANSTO has also adopted the following working definition
described in IAEA Safety Series No. 111-G-1.1, Classification of Radioactive Waste 1994 (section
318):- Low level wastes (liquids and solids) have a dose on contact < 2 mSv/h- Intermediate level wastes (liquids and solids) have a dose on contact > 2 mSv/h. Shielding
must be employed for all processes and storage facilities where intermediate level wastes are
involved
For long term waste disposal purposes offsite (to the proposed Commonwealth Radioactive
Waste Management Facility), the above definition does not apply and all wastes are to beclassified and managed according to ARPANSA’s system (RPS 20).
2.3.2 Radiological Protection for Radiation Workers
Refer to ANSTO Guide Docs
2.3.3 Radiological Protection for Radiation Area
Refer to ANSTO Guide Docs
2.3.4 Radiological Protection for the PublicRadioactive waste management controls and the control of radioactive discharges are in placein all jurisdictions to current international standards.

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FNCA Consolidated Report on Radiation Safety (Australia)

2.3.5 Radiation Emergency Preparedness
ARPANSA maintains two offices with Scientific (Melbourne) and Regulatory (Sydney) units.
Radiation Emergency Planning is coordinated by the Health Physics Section of the Environmental andRadiation Health Branch, Melbourne. The coordination of Commonwealth response to State requests
for radiation emergency support is through Emergency Management Australia (EMA).
In the event of a radiation accident or radiation emergency, and when requested by the responsible
State or Commonwealth authorities, ARPANSA can provide Health Physics Advisors and Health
Physics monitoring teams. In 1989, ARPANSA was designated jointly with the Peter MacCallum
Cancer Institute as a Collaborating Centre for Radiation Protection and Radiation Emergency Medical
Assistance (CRPREMA), and is a member of the WHO Radiation Emergency Medical Preparedness
and Assistance Network. This role requires that ARPANSA assist in training and dissemination of
information on response to radiation accidents and emergencies, as well as respond to WHO requests
for assistance for radiation accidents and emergencies in neighbouring countries. (REAC/TS in the US
is also a member of REMPAN.)
Through ANSTO, ARPANSA are part of the IAEA EMERCON Network for assistance ininternational response to radiation emergency. ARPANSA maintains an Australia-wide network of
fallout monitoring stations as part of the Comprehensive Test Ban Treaty (CTBT) network ofmonitoring stations.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

2. Bangladesh
Part 1. Radiation Safety in Radioisotope Facilities ............................................................. 17
1.1 General ................................................................................................................... 17
1.1.1 Legislative and Statutory Framework ...................................................................... 17
1.1.2 Structure of Regulatory Authority ........................................................................... 18
1.1.3 Legal Background ................................................................................................. 18
1.2 Outline of Radiation Facilities and Radiation Sources ................................................. 19
1.2.1 Number of Specialists and Workers in Related Organizations
and Radiation Facilities including Related Facilities ..................................................... 19
1.2.3 Activity and Number of Radiation Sources and Generators ....................................... 19
1.3 Education and Training............................................................................................. 20
1.3.1 RI Usage............................................................................................................... 21
1.3.2 Radiological Protection.......................................................................................... 21
1.4 Standardization on Radiation and Radioactivity .......................................................... 21
Part 2. Status of Radiation Safety Management ................................................................. 21
2.1 Radiation Safety Management in various RI Usage..................................................... 21
2.1.1 Radiation Protection Programme ............................................................................ 21
2.1.2 Radiation Emergency Preparedness ........................................................................ 22
2.2 Radiation Safety Management in Research Reactors ................................................... 23
2.2.1 Radiological Protection for Radiation Worker, Radiation Area, and Public ................. 23
2.2.2 Radiation Emergency Preparedness ........................................................................ 24
2.3 Radiation Safety Management in Nuclear Power Plants .............................................. 24
2.4 Radiation Safety Management in Radioactive Waste Management ............................... 24

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

2. Bangladesh
Part 1. Radiation Safety in RI Facilities
1.1 General
Bangladesh Atomic Energy Commission (BAEC) follows the IAEA Safety Series No. 115(1996), USNRC Code for radiation protection, the recommendations of the international
Commission on Radiological Protection (ICRP) and the Nuclear Safety and Radiation Control
Rules (SRO NO. 205 –Law/97). The overall safety objective is to protect operating personnel,
society and the environment by establishing and maintaining an effective defence against
radiological hazards. The safety objectives of the radiation protection policies are as follows: To ensure that the operation and utilization of nuclear/radiation facilities is justified underradiation protection consideration
 To ensure that during normal operation radiation exposure of site personnel and public
remains below limits prescribed by national authorities and is kept ALARA
1.1.1 Legislative and Statutory Framework
The Regulatory Authority of Bangladesh is authorized for issuing rules and regulations andconducting licensing and supervisory processes for issuing licenses, and thereby regulating
nuclear and radiation safety for siting, design, equipment manufacturing, construction,commissioning, operation and decommissioning of nuclear/radiological facilities. Nuclear Safety
and Radiation Control Division (NSRCD) is also responsible for the regulation of issues related toaccounting and control of nuclear materials, radioactive substances and physical protection. The
NSRCD is the competent authority for licensing shipments out of Bangladesh and giving consent
to shipments into Bangladesh.
The basic legal and statutory framework for Nuclear Safety and Radiation Control is in place.
The present legislative framework does not separate the regulatory functions from promotional
activities of the BAEC and together with its NSRCD, the Commission performs both. A draft
Nuclear Safety Law has been submitted to the Agency for comments and it is currently under the
Agency's review (October 2008). It is expected that the draft Nuclear Law when promulgated will
have full provisions for public and environmental radiological protection, although the regulationsof public exposure is presently covered by an existing NSRC Rule-97.

17

FNCA Consolidated Report on Radiation Safety (Bangladesh)1.1.2 Structure of Regulatory Authority

Fig.1: Structure of Regulatory Authority

1.1.3 Legal Background
National policy is to provide adequate protection for man and the environment against undue
exposure to ionising radiation from radiation sources and radioactive wastes for the present and future
generation. Nuclear Safety and Radiation Control Act 1993 was duly approved and enacted (1993) and
the Regulations have been put into force (1997).
The following acts that address the basic nuclear activities have already been approved by theGovernment of Bangladesh. This act will establish the set up basic requirements for managementof radioactive waste; define basic requirements, licensing procedures and responsibilities ofdifferent organizations involved in nuclear activities and related radioactive waste management.
 Nuclear Safety and Radiation Control Act 1993, Act No. XXI of 1993,
 Nuclear Safety and Radiation Control Rules – 1997 SRO. 205 – Law/97,
Date: September 04, 1997
The Radiation Protection Regulations contains information on clearance and sets up clearance
levels and limits for authorized discharges of radioactive substances from nuclear facilities. In
addition, Nuclear Safety and Radiation Control Division (NSRCD) have prepared new rules for the‘Radioactive Waste and Spent Fuel Management – 2008, which is currently under the Agency’s
review.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

1.2 Outline of Radiation Facilities and Radiation Sources
1.2.1 Number of Specialists and Workers in Related Organizations and Radiation Facilities
including Related Facilities
Refer to the table 1.
Table 1: Number of specialists and workers in related organizations and radiation facilities
Approximate Number of
Numbers (Installation/unit)
specialist/worker
Diagnostic X-ray units
3800
5500
Research Reactor

1

20

Dental X-rays

150-

Nuclear medicine departments

18

122

Radiotherapy facilities

12

100

Teletherapy

12-

Brachytherapy

7-

Industrial radiography facilities

14-

Industrial or research irradiators

3-

Nuclear gauges

38-

Well-logging devices

7-

neutron generator

1

2

Radioisotope production unit

1

12

Tandem accelerator

1

15

Beach sand mineral processing plant

1

10

Waste storage facility

1

19

Research laboratories

11-

Linear Accelerator

13

20

1.2.3 Activity and Number of Radiation Sources and Generators
Refer to the following table 2-5.
Table 2: Nucleonic Gauge practices
Sl. NoActivity

Units

01

241

50 mCi – 03 Ci

18

02

60

10-50 mCi

04

03

137

Cs

20-500 mCi

06

04

90

Sr

25 mCi each

10

05

85

Kr

50 mCi – 01 Ci

08

Am-Be

10- 50 mCi

08Fe

100 mCi

01

Ni

200 mCi

01

06

Source/Machine
Am
Co

07

55

08

63

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

Table 3: Nuclear Well-logging Practices
Sl. No01

SourceActivity

Units

Am-Be

20Ci- 20 Ci

12Cs

50 mCi- 02 Ci

07

Th

0.23 Ci

02

02

137

03

232

04

226

Ra

2.5 Ci

02

05

60

Co

01- 2.5 Ci

30

Sl. NoSourceActivity

Units

01

192

Ir

45 – 102 Ci

09

Cs, for controlling X-ray Crawlers

20 mCi each04

Industrial X-ray Machines

upto 300 kVp

07

Table 4: Industrial Radiography practices

137

02
03

Table 5: Nuclear Medicine Facility
Sl. No.

SourceActivity

01

125

I

02μCi – 02mCi

02

131

I

20 – 200 mCi

03

99m

Tc

100 – 405 mci

04

90

Sr

55mCi each – 13 units

05

137

06

32

P

10 – 100 mCi, 3 units

07

67

Ga

10 – 50 mCi, 3 units

08

201

09

Cs

11 μCi – 345 mCi

Tl

186

90

Re Yt,

133

51

57

10 – 20 mCi, 3 units
58

60

Xe, Cr, Co, Co, Co,

153

Sm

1.3 Education and Training
BAEC regularly arranges 3 months long Basic Nuclear Orientation Course for its newly
recruited scientists. This course covers the fundamentals of all the areas of BAEC programs. Shortduration specialized courses involved lectures, practical classes, workshop, seminar, conferences
etc. are arranged. In addition, government of Bangladesh or other agencies like International
Atomic Energy Agency (IAEA), Ministry of Education, Sports, Science and Technology (MEXT),
Germany Academic Exchange Service (DAAD), Colombo Plan, International Centre for
Theoretical Physics (ICTP) and other international organizations also provide the training for
BAEC Scientist.
The training programmes for the radiation protection and management are provided by the
NSRCD for the Radiation Control Officers (RCO’s), radiation protection management staff, otherfacility personnel.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

1.3.1 RI Usage


Production of radioisotopes: (e.g.99mTc,131I )

Agriculture: 65Zn, 32P, 54Mn, 3H, 35S and 14C



Research:137Cs,60Co,226Ra,241Am,131I,90Sr,22Na,192Ir, 152Eu etc.






Industrial Radiography practices: 192 Ir, 137Cs
Nuclear Well-logging Practices: Am-Be, 137Cs, 232Th, 226Ra, 60Co
Nucleonic Gauge Practices: 241 Am 60Co, 137Cs, 90Sr, 85 Kr, Am-Be, 55 Fe, 63 Ni
Nuclear Medicine Facility: 125I, 131I, 99mTc, 90Sr, 137Cs, 32P, 67Ga, 201Tl, 186Re 90Yt, 133Xe,
51
Cr, 57Co, 58Co, 60Co, 153Sm

1.3.2 Radiological Protection
The legislative basis for radiation protection in Bangladesh consists primarily of the
President’s Order No.15 of 1973 establishing the Bangladesh Atomic Energy Commission(BAEC); the Nuclear Safety and Radiation Control Act No.21 of 1993; and the Government Order
HM/hospital-1/ap-2/2001 issued on 01/12/2001 transferring the control of x-ray machines from
the Ministry of Health and Family Welfare to the BAEC. The regulatory function is exercised by
the Nuclear Safety and Radiation Control Division (NSRCD), which is an integral part of the
BAEC. The Nuclear Safety & Radiation Control (NSRC) Act of 1993 and the NSRC Rules–1997,(SRO NO-205-Law/97) stipulate that licensees engaged in activities involving normal exposure orpotential exposure are responsible for the protection of the employees from occupational exposure.
The provision of individual monitoring services is mandatory. A national system (logistics and/or
technical capabilities) for monitoring the levels of radioactivity in foodstuffs and selectedcommodities before they are traded exists.
1.4 Standardization on Radiation and Radioactivity
Standardization and Calibration of radiation measuring instruments and dosimeters for
performance tests are carried out using SSD laboratory at Atomic Energy Research Establishment(AERE), Savar. The Calibrated instruments and sources traceable to a primary standard laboratory.
Participation in the IAEA intercomparison programs largely contributed to the improved accuracy
and reliability on radiation and radioactivity measurement.

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Management in various RI Usage
The operating organizations establish and implement a radiation protection programme toensure that all activities involving radiation exposure are compliance with regulatory
requirements.
2.1.1 Radiation Protection Programme
The operational radiological safety programme of the research reactor and othernuclear/radiation facilities are carried out following the IAEA/NSRC regulation. Bangladesh
Atomic Energy Commission (BAEC) ensures the safety and radiation protection of man and the21

FNCA Consolidated Report on Radiation Safety (Bangladesh)

related environment through the following radiological protection services: Radiation/contamination survey of all potentially radioactive/contamination areas Personnel monitoring of all radiation workers: TRF, casual workers and visitors
 Classification of supervised and controlled areas
 Environmental monitoring of all work places where air-borne radioactivity is likely to be generated
 Records keeping pertaining to all kinds of monitoring Safety evaluation of radiation workers and assessment of radiological risks
 Approval of activities, which involve actual or potential exposure to radiation or release ofradioactive material to the environmentRegular calibration of radiation monitoring instruments and records keeping
Formulation of safety procedures for the safe handling of radioactive materials and radiation
sourcesSafe management of radioactive waste
Control over the internal movement of radioactive materials to and from the TRF radiation areas
Advice on matters related to radiation protection
Medical services
Training

To ensure that accidents are generally prevented, the legal dose limits for both occupationally
exposed personnel and the general public, as mentioned in the NSRC Rules 1997 are described in
the table below:
Table 6: Effective dose and annual dose limit for occupational worker and general public

Application
Effective dose

Effective dose

Annual equivalent doseto
The lens of the eye
The skin
The extremities

Dose limits
Occupational workers
20 mSv per averaged
over five consecutive
years

General public
1 mSv in a year

50 mSv in any single
year

5 mSv in any single year, in special
circumstances, provided that the
average dose over five consecutive
years does not exceed 1 mSv/yr.

150 mSv
500 mSv
500 mSv

15 mSv
50 mSv
50 mSv

2.1.2 Radiation Emergency Preparedness
The Nuclear Safety and Radiation Control Division (NSRCD) in cooperation with BAEC’s
Health physics and radiation-monitoring laboratories has been assigned to provide expertise andservices in radiation protection. Capabilities for regular training of emergency personnel are being
developed under national emergency plan. However, some capabilities have already beendeveloped through training of relevant manpower in home and abroad. A draft national
radiological plan is currently under review. One national committee, two subcommittees and one

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

local subcommittee have been formed to perform responsibilities during radiological emergency.
2.2 Radiation Safety Management in Research Reactors
The operational radiological safety programmes of the research reactor are carried out
following the IAEA/NSRC regulation. All radiation surveys are carried out by group member ofradiation protection and RCO (Radiation Control Officer) maintain proper record.
2.2.1 Radiological Protection for Radiation Worker, Radiation Area, and Public
Assessment and control of radiation exposure to occupational workers and the public are
performed under the ERM program. Radiation measurement for TRF (tritium reduction facility)
worker is currently carried out by TLD (Thermoluminescent Dosimeter) techniques on a quarterly
basis. All TLD’s are checked/measured for evaluation of dose level for all occupational workers at
TRF. Pocket dosimeters are also used if high dose rates are probable.






The frequency of radiation surveys are determined by RCO depending on thenature and scale of operations carried out in the area
Area in which radiation sources are used or stored interim storage room, heatexchange room, ion exchange resin bed, primary pump room, decay tank entrance
door, fresh fuel storage room, reactor control room, reactor hall, reactor top,
neutron spectrometry laboratory, tangential beam port area, piercing beam port,
radial beam ports, rabbit room, etc. are monitored in regular intervals.
A high-resolution gamma spectrometry system is used to analyze food andenvironmental samples.
The gaseous radioactive effluents from TRF discharged through the stack aremonitored before discharging to atmosphere[Access control and zoning]

Areas where potential radiological risks from radiation or contamination are
designated as control areas, which are further, classified as radiation area, contamination
area or both. Areas in which sealed radiation sources are used or stored and radiation
generating apparatus are in operation classified as radiation zones. Similarly, the areas inwhich unsealed radioactive materials are handled designated as radiation andcontamination zones.
Supervised areas are any areas where occupational exposure conditions need to be
kept under review even though specific protective measures and safety provisions are notnormally needed.
All controlled areas are marked with appropriate warning signs in order to indicate thepresence of ionising radiation or radioactive contamination or both. All the person
entering the controlled areas are required to wear radiation personnel monitoring devices
such as TLD’s or pocket dosimeters and protective clothing.
On account of external and internal radiation risks the areas have been declaredcontrolled/supervised areas:

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

Location

Designated Areas

Reactor top

Controlled area

Reactor Hall
Control room

Controlled area
Supervised area

Public gallery
Reactor Manager Office

Supervised area
Supervised area

Laboratory room

Supervised area

Staff Sitting room

Supervised area

Senior reactor operator sitting room

Supervised area

Officers sitting room

Supervised area

Spare parts store room
Neutron spectrometer lab

Supervised area
Supervised area

Staff sitting room (Ground floor)

Supervised area

Health physics control room

Supervised area

Rabbit room (ground floor)

Controlled area

Fresh Fuel storage room
Radioactive waste storage room

Controlled area
Controlled area

Heat exchanger room (ground floor)

Supervised area

Primary pump & decay tank room
Stack (Ground floor)

Supervised area
Supervised area

Stack (1st floor)
Stack (2nd floor)
Stack (3rd floor)

Supervised area
Supervised area
Supervised area

Table 7:

Location of radiation control and supervised area at TRF

2.2.2 Radiation Emergency Preparedness
The availability of the resources and tools required for responding to the emergencies has been
ensured. The personnel are being trained continuously through testing of the emergency plans andprocedures, taking part in the emergency exercises and publishing the appropriate information. As
a result of the feedback of the experiences gained during the exercises, the emergency plans arebeing reviewed and improved. A complete organisatioal infrastructure of radiation emergency
preparedness is in the development process.
2.3 Radiation Safety Management in Nuclear Power Plants
Currently, there is no power reactor in Bangladesh. It has one 3 MW TRIGA Mark II research
reactor at Savar site.
2.4 Radiation Safety Management in Radioactive Waste Management
 General Safety Provisions for Radioactive Waste
In Bangladesh, radioactive wastes generated mainly from activities of research reactor
operation, radioisotope production, nuclear medicines, industrial applications and other nuclear
researches. These wastes are classified into low level radioactive waste and intermediate level
radioactive waste. Criteria used to define and categorize radioactive wastes bases on theclassification system as recommended by the IAEA. All radioactive wastes, including disused

24

FNCA Consolidated Report on Radiation Safety (Bangladesh)sealed sources, are kept to a minimum, adequately processed, stored or disposed of underregulatory control.
 Radiation Protection Policy
During all operation states, the main aim of radiation protection is to avoid any unnecessary
exposure to personnel and to keep unavoidable exposure as low as reasonably achievable(ALARA). The radiation exposure of site personnel and members of the public conforms to therequirements of relevant authority (Rules).
For accident conditions the radiological consequences are mitigated by appropriate engineered
safety features, by accident management procedures and by the means provide in the emergency
plan.
Operating organization is responsible fora) Appropriate control of radiation doses to persons resulting from the operation.
b) Appropriate control of the amounts of radioactive substances released to the environment
from the facility and off – site radiation dose levels.
c) Preparations for the management of on-site emergencies and co-operation withappropriate authorities during off - site emergency
The radiation protection programme includes adequate administrative measures, which takeaccount of the design provision for:a) Restricting the exposure of site personnel and of the general public within, establishedlimits and the ALARA concept.
b) Ensuring that there is sufficient and appropriate instrumentation and equipment for
personnel monitoring and protection.
c) Ensuring that there is on site radiological monitoring and surveying.
d) Ensuring that there is on - site cooperation between the radiation protection staff andoperating staff in establishing operating and maintenance procedures when radiation
hazards are anticipated and direct assistance will be provided when required.
e) Providing for environmental radiological surveillancef) Providing for decontamination of personnel equipment and structuresg) Controlling compliance with applicable regulation for the transport of radioactive
materials.
h) Detecting and recording any release of radioactive materiali) Recording the inventory of radiation sources.
j) Providing adequate training in radiation protection practices.
All facility personnel are individually responsible for putting into practice the exposure control
measures within their area of activity, which are specified in the radiation protection programme.
Consequently, particular emphasis is given to all facility personnel to ensure that they are fully
aware of both the radiological hazards and the protective measures available. Special attention is
given to the fact that, personnel at the facility may include persons not permanently working there(e.g., experimenters, trainees, visitors and outside workers).
The operating organization verifies by means of surveillance, inspection and audits, that theradiation protection programme is being implemented and that its objectives are achieved, andundertakes corrective action if necessary.

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If reference level is exceeded, the operating organization investigates the matter for the
purpose of taking corrective action.
All personnel who may occupationally be exposed to significant levels of radiation have their
exposure measured, recorded and assessed as determined by the relevant authority and this record
is available to the regulatory body or to any other body designated by the national regulations.
If the limits for either personnel exposure or radioactive release are exceeded, the regulatory
body and/or relevant authority informs in accordance with the requirements.
The radiation protection programme provide for the medical surveillance, the personnel who
may be occupationally exposed to significant radiation doses. The legal dose limits for both
occupationally exposed personnel and the general public are described in the table below:
Application

Occupational

Public20 mSv(averaged over defined periodof 5 years)

1 mSv(averaged over any consecutive
years 5mSv

Annual equivalent dose in thelens of the eye

50 mSv in any single year

15 mSvAnnual equivalent dose to
extremites (hand or feet) or theskin

500 mSv

15 mSv

Effective dose per year

Table 8:

Effective dose and annual dose limit for occupational worker and general public Personal Monitoring
The essential aim of radiological protection is to prevent injury from ionizing radiation. It’s
basis respects for the recommended maximum permissible doses, but also calls for systematic
observation to detect any radiation or irradiation effect. Radiation measuring devices (e.g., pocket
dosimeter, TLD for individual radiation measurement) are worn by the facility personnel. Gamma
spectrometry and radiation detectors system are also available in this unit for determination of thepresence and quantity of radioactivity.
 Area Monitoring
For administrative purposes, disposal to the environment during routine operation is limited toclearance level for all radioisotopes.
It is the policy of Central Radioactive Waste Processing and Storage Facility (CWPSF)
operation group does not to release radioactive material above naturally existing amounts to any
stream or ground water under normal operation conditions. The content of radioactivity in thetreated wastes is checked to determine the concentration of radioactivity.
The solid wastes are collected and located on controlled area of the CWPSF for accumulationof clean and low - level contaminated waste.
Air sampling of site are taken weekly by health physics staff and the results are recorded. All
equipment and areas are monitored by group member of radiation protection and reported to RCO
for proper record keeping.
The Gamma Area Monitoring System is used for monitoring of radiation level in various parts ofoperation area. Each detector has a Geiger Muller detector as radiation sensor. The following is a

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list of equipment available area monitoring:a) Portable survey metersb) Portable air samplerc) Geiger Muller Counterd) Portable gamma analysise) Portable Dose - rate meter Environmental Monitoring
Air samples are collected and analysed in several locations within CWPSF, AERE andevaluation of radioactivity in these samples is done in regular basis. Background radioactivity
around the setting locations of CWPSF, AERE are measured and evaluated every month.
 Emergency Preparedness
The operating organization is developing the capabilities for protection of the public and theenvironment by establishing policies, strategies and programme involving radiation exposure andradiological consequences due to accident conditions.

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3. China
Part 1. Radiation Safety in Radioisotope Facilities ............................................................. 29
1.1 General ................................................................................................................... 29
1.1.1 Legislative and Regulatory Framework ................................................................... 29
1.1.2 Regulatory Body ................................................................................................... 29
1.2 Outline of Radiation Facilities and Radiation Sources ................................................. 31
1.2.1 Authorization ........................................................................................................ 31
1.2.2 Workers and Specialists in Radiation Facilities......................................................... 31
1.2.4 Recent Movement Concerning Radioisotope Sources............................................... 32
1. 3 Education and Training ............................................................................................ 32
1.3.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc....... 32
1.3.2 The Nuclear Reactor and Fuel Law ......................................................................... 33
1.3.3 Examples of Education and Training....................................................................... 33
1.4 Standardization on Radiation and Radioactivity .......................................................... 34
Part 2. Status of Radiation Safety Management ................................................................. 34
2.1 Radiation Safety Control in RI facilities ..................................................................... 34
2.1.1 Radiation Safety Control System ............................................................................ 34
2.1.2 Radiation Protection of Workers ............................................................................. 35
2.1.3 Radiation Protection of Working Area ..................................................................... 35
2.1.4 Public Radiation Protection .................................................................................... 36
2.1.5 Emergency Action ................................................................................................. 36
2.2 Radiation Safety Management in Nuclear Facility ...................................................... 37
2.2.1 Radiation Safety Management System .................................................................... 37
2.2.2 Radiological Protection for Radiation Worker .......................................................... 38
2.2.3 Radiation Area Management .................................................................................. 39
2.2.4 Radiation Protection for Public ............................................................................... 40
2.2.5 Nuclear Emergency Response ................................................................................ 41

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3. China
Part 1. Radiation Safety in RI Facilities
1.1 General
1.1.1 Legislative and Regulatory Framework
The legislative framework in China regarding radiation safety is composed of national laws,
administrative regulations, and department rules.
The existing national laws applicable to the field of nuclear safety and radiation safety are:1) The Law of the People’s Republic of China on Environmental Protection;2) The Law of the People’s Republic of China on Prevention and Control of Radioactive
Pollution; and
3) The Law of the People’s Republic of China on Environmental Impact Assessment
The Law of the People’s Republic of China on Environmental Protection was promulgated in 1989
by the Standing Committee of the National People’s Congress. It is a specific law applicable toprotecting and improving accessible environment, preventing and controlling pollution, protecting
health of people, and advancing social progress. The Law of the People’s Republic of China on
Prevention and Control of Radioactive Contamination was promulgated in 2003 by the Standing
Committee of the National People’s Congress. This law is applicable to the prevention and control ofenvironmental pollution that are caused by the discharge of gaseous, liquid and solid wastes in thecontext of nuclear energy expansion, nuclear technology applications, mining of uranium/thorium
resources and ores associated with radioactivity, so as to attain the goals of preventing and controllingradioactive pollution, protecting the environment and health of people, and accelerate the development
and peaceful use of nuclear energy and nuclear technology.
1.1.2 Regulatory Body
In China, the independent regulatory bodies which are relevant to radiation safety are Ministry ofEnvironment Protection (MEP(NNSA-National Nuclear Safety Administration)), Ministry of Healthand Ministry of Public Security.
 MEP/NNSA Responsibilities
MEP (NNSA) undertakes the overall regulation of the country-wide prevention and control ofRadioactive Pollution, through review and authorization, supervision and inspection, and supervisory
monitoring of the activities associated with license holders. Thus it can be ensured that the license
holders assume the responsibility of safety and conduct activities in compliance with relevant laws andregulations. MEP (NNSA） is principally responsible for:1) Drafting and establishing policy, strategy and regulations relevant to nuclear safety, radiation
safety, prevention and control of radioactive pollution, and coordinating development andpublication of relevant standards;
2) Licensing and regulating of nuclear safety, radiation safety and prevention and control ofradioactive pollution;3) Investigating and tackling nuclear safety accident and radiation safety accident, in cooperatingwith other relevant organizations in providing guidance on, and supervision of the preparation

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and implementation of NPP emergency plan, and working with other relevant organization inparticipating with nuclear accident emergency through the conciliation and resolution of the
dispute relating to nuclear safety;4) Conducting review, authorization, supervision and inspection of environmental impact
assessment;5) Supervisory monitoring the discharge of radioactive effluents and radiation environmental
release; and
6) Planning and coordinating relevant scientific research and promoting dissemination of relevant
knowledge.
 Ministry of Health
The main responsibilities of the Ministry of Health1) Developing health related regulations and standards for radiological workers;2) Supervising the doses that may be received by the radiological workers;3) Reviewing and authorizing occupational health/hygiene assessment; and
4) Organizing the radiological injury diagnosis and treatment and the medical rescue in the caseof nuclear and radiation accident.
 Ministry of Public Security
The Ministry of Public Security is principally responsible for investigating and recovering thelost radioactive sources, and for the security of road transport of radioactive materials.
 Functions of China Atomic Energy Authority
In addition to the forgoing mentioned regulatory bodies, the China Atomic Energy Authority(CAEA) is one of the primary governmental agencies relevant to radiation safety, with the following
functions:
1) To research and draft out policies and regulations for peaceful utilization of atomic energy inChina;
2) To research and establish developing program, planning, and nuclear industry standard forpeaceful utilization of atomic energy in China;
3) To organize demonstration, review and approval of relevant science and technology research
project on peaceful utilization of nuclear energy in China; be in charge of surveillance andcoordination of the implementation of science and technology projects;
4) To be in charge of control of nuclear materials and physical protection of nuclear installations;5) To be in charge of review and management of nuclear export;
6) To be in charge of communication and cooperation in nuclear energy field among
governments and also among international organizations; take part in the IAEA and its related
activities on behalf of Chinese government;7) To undertake emergency management of state nuclear accidents and lead on organizing the
National Coordinating Committee for nuclear Emergency, be in charge of developing,
preparing and implementing national nuclear accident emergency plan;8) To be in charge of the decommissioning of nuclear installations and the treatment ofradioactive waste.

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1.2 Outline of Radiation Facilities and Radiation Sources
1.2.1 Authorization
All radiation sources-related production, sale, transfer, use, import, and export shall be
subjected to the licensing system. MEP(NNSA) and the bureaus of environment protection at
provincial level, observing principles of categorizing radiation sources and regulations in thisrespect, separately exercise rights of approval and documentation.
The categorization of radiation source in China is principally equivalent to the IAEA’s
categorization. Based on the potential hazards on human and environment, radiation sources are
divided into five categories. For organizations that produce radioisotopes or sell and use categorysources, MEP(NNSA) takes direct responsibilities of reviewing, approving and granting licenses.
Authorities concerned at provincial level grant licenses for the rest of radioactive sources.
1.2.2 Workers and Specialists in Radiation Facilities
1.2.2.1 Radiation Workers
The number of people working with radiation related industry in China is difficult to correctly
define, according to an incomplete statistics, 300 thousand people are engaging in the utilizationof nuclear technology.
1.2.2.2 Radiation Protection Supervisors
The MEP(NNSA) is the government authority responsible for radiation safety. The MEP(NNSA)
has six regional branches in Shanghai, Shenzhen, Chengdu, Beijing, Lanzhou and Dalian, respectively,
which are responsible for routine supervision of nuclear safety and radiation safety in designated areas.
In order to fulfill a better implementation of regulatory functions, MEP (NNSA) set up a Nuclear andRadiation Safety Center as technical support and guarantee for itself. An expert panel concerning
nuclear safety and the environment was set up to provide technical support in aspects of drafting nuclear
safety and radiation safety laws and regulations, decision-making, technical development, technicalreview and supervision. MEP (NNSA) has nearly 1000 staff in total now.
In order to ensure and maintain the capability of regulatory staff, it is required that the staff shallmeet the follow conditions:1) Have a bachelor’s degree or above or at the same educational level;2) Have gained more than 5 years of practical experiences or more than 3 years of experiences innuclear(radiation) safety management, being able to fulfill the task of nuclear(radiation)
safety supervision under the rule of relevant law and regulations independently, and be able to
make correct judgment and write qualified report;
3) Be familiar with national nuclear (radiation) safety regulations and complying with therelevant national laws and regulations; and
4) Be honesty, just, devoted and modesty.
1.2.2.3 Activity of Radiation Sources and Number of Generators
In China, application of sealed sources started in the 1930’s. Documentation has shown thatthe earliest radioactive source found in China is radium needles used in a hospital in Beijing. With
the dramatic expansion of nuclear technology and the increasing development of economy, inparticular since the 1980’s, the use of sealed radioactive sources is rapidly expanding in China.
According to an incomplete statistics, the number and quantity are increasing at 10% rate per year
in the recent years. As of December 31, 2006, the total number of the producers, vendors and users

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of radioisotopes amount to about 13051 across the country, with more than 140,000 of sealed
sources involved in total.
1.2.4 Recent Movement Concerning Radioisotope Sources
1.2.4.1 Develop Conditioning Capability for Spent Radioactive Source
Spent radioactive sources are currently held in the provincial nuclear application wastes
storage facilities and in the centralized radioactive source storage facility or at user’s premises.
These radioactive sources have not been conditioned into a stable form, which occupy large
storage space and pose high potential risk. China is making effort to establish a research anddevelopment base to develop radioactive source conditioning technology as soon as possible forthe purpose to improve the safety of radioactive source storage. At the same time, China is
exploring options for disposal of spent radioactive sources, it is expected to seek a long termsolution for spent radioactive sources. .
1.2.4.2 Promote Disposal of LILW
In accordance with the Law of the People’s Republic of China on Prevention and Control ofRadioactive Pollution, China is organizing to develop the siting program for solid radioactive
waste disposal. This will help analyze the demands for solid LILW disposal in a comprehensive
manner and direct the development trend of solid LILW disposal and promote the development ofregional disposal site for LILW.
1.2.4.3 Promote Minimization of Radioactive Waste
One of the principles and objectives for radioactive waste management is to control thegeneration of radioactive waste so as to achieve the minimization of radioactive waste in China.
The expansion of nuclear power in China raised a high requirement for safety of radioactive waste
management. As a result, facilitation of radioactive waste minimization is a sustainable work
Chinese government faces. Compared with advanced countries, there are still larger potentials to
reduce waste generated at NPPs. However, the minimization of radioactive waste is a combined
effort balancing factors of technology, safety and economy. China will take more action incontrolling generation of waste, upgrading management, introducing advanced waste reduction
technology, promoting specialization and socialization in radioactive waste treatment service.
1. 3 Education and Training
1.3.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc.
Under Article 28 of Regulations on Safety and Protection against Radioisotope andRay-generating Installations, any undertakings who produce, distribute and use the radioisotope
and ray-generating installations shall provide training in nuclear safety and protection knowledge
to the workers who is directly associated with production, distribution and use of them.
Examination shall be given to the trainee. The worker who does not passed the given examination
is not fit the job post with radiation safety related responsibility. The training program, in
conjunction with training materials, was developed by the MEP in such a way as to have an
enhanced training management and consistent training and examination requirements. Training
organizations have been accredited with whole process supervision being provided of training andexamination.

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1.3.2 The Nuclear Reactor and Fuel Law
Recruitment, training and re-training of nuclear facility operational personnel and authorization are
subject to the nuclear safety guideline “Staffing, Recruitment, Training and Delegation at NPPs”.
As required by the relevant regulations, guidelines, and standards, the requirements for post
qualification is defined, on the basis of the post-specific task analysis, and the training and retraining
program and procedures are developed and implemented. The personnel working in nuclear facilities
can carry out the relevant post with responsibility only after appropriate training, qualification
examination, and acquirement with post qualification certificate or authorization granted.
Validity period management is applied to the qualification and authorization for nuclear facility
personnel. After expiration of effective period, the extension and renewal of qualification certificate
shall be made in accordance with the post-specific requirements. Furthermore, additional training andre-training are needed to ensure for the personnel to meet the post-specific requirements.
With the expansion of nuclear power production in China, systematic training approach is being
drawn on at nuclear facilities. Training demand analysis is based on the actual work conditions. Withfocus on the safe operation of nuclear facilities, different types of training and technical support
activities are carried out in so far as to continue to raise the level of knowledge and competence of
nuclear facility’ personnel. Training resources are optimized through standardizing teaching material
preparation. Trainer management and cultivation are strengthened by many approaches. The internaland external evaluation and feedback are conducted to continue the improvement of the existing
training system.
1.3.3 Examples of Education and Training
In order to raise the quality of the technical staff for nuclear safety related activities, Chinese
government, in November 2002, issued the Temporary Regulations on Registration qualifications for
Nuclear Safety Engineer under which the occupational qualification system was established for thetechnical staff working on the key nuclear safety related posts who are providing nuclear safety related
technical services for the nuclear energy and nuclear technology applications. It was issued consistent
with the relevant provisions of the Law of the People’s Republic of China on Prevention and Control ofRadioactive Pollution to enhance the management of the key posts with nuclear safety related
responsibility, ensure nuclear and radiation environmental safety, and maintain national and the public’s
interests. Subsequently, Nuclear Safety Engineer Registration Management Rules was issued in 2004,
and the Temporary Regulations on Continued Education of Registered Nuclear Safety Engineer was
issued in 2005.
Country-wide examination is sponsored annually for applicants for registration qualification after
being given systematic training and qualification certification. The subjects to be examined cover
nuclear safety related laws and regulations, nuclear safety related comprehensive knowledge, nuclear
safety related practices and nuclear safety case analysis. Qualification Certificate of the People’s
Republic of China for Registered Nuclear Engineer is granted to the qualifier after his or she passed thegiven examination. The validity period of a registration is 2 years. Continued educational regime isperformed for the registered nuclear safety engineers.
The occupational scope of a registered nuclear safety engineer covers review of nuclear safety case,supervision of activities affecting nuclear safety, manipulation and operation of nuclear facilities,
quality assurance, radiation protection, radiation environmental monitoring, and other nuclear safety
closely related fields prescribed by the MEP(NNSA) .

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1.4 Standardization on Radiation and Radioactivity
In China, standard is one part of the legislation and regulation. Chinese government has
attached high degree of importance to the legislation and regulation of nuclear and radiation
activities, thus leading to the continued improvement of the legislation and regulation system. In
1960, the Regulation on Health and Protection for Work with Radioactivity was promulgated.
Subsequently in 1974, Regulation on Radiation Protection（GBJ8-74）was issued. In 1979, theLaw of the People’s Republic of China on Environmental Protection (for trial) was promulgatedfor implementation, stipulating that the design, construction and operation of a main project mustbe simultaneous with those of the facilities used for preventing pollution and other public hazards.
In 1986, the State Council issued the Regulation on the Safety Control for Civilian Nuclear
Installations, establishing the nuclear facility licensing system, and setting up independent
regulatory body for nuclear facility safety. In 1989, the State Council issued the Regulations on
Safety and Protection of Radioisotope and Ray-generating Installations, stating that licensing
system shall be applied to the production, distribution and use of radioactive sources and therecovery and storage of disused radioactive sources. Various administrative departments under theState Council relating to health, environmental protection and public security shall apply phased
regulation to the radiation protection in the production, distribution and use of radioisotopes. The
environmental protection competent authority under the State Council is responsible for the
regulation of the recovery and decommissioning of radioactive sources. In 1992, the State Council
approved and circulated the Environmental Policy on LILW Disposal in China (State Council[1992]45), which strongly boosts the matters relevant to radioactive waste disposal. In 1993, theState Council issued the Regulations on Accidental Emergency Management at Nuclear Power
Plant, setting out the policies, strategies and measures to be adhered to in the event of an
emergency. In 2003, the Law of the People’s Republic of China on Prevention and Control ofRadioactive Pollution was promulgated for enforcement. It defines that the environmental
protection competent authority under the State Council has the overall responsibilities for thecountry-wide prevention and control of radioactive pollution by virtue of the relevant nationallaws and that other administrative departments under the State Council shall implement their
allocated duties in this regard. In 2004, the State Council caused the Regulations on Protection
against Radioisotope and Ray-generating Installations of 1989 to be revised, and renamed
Regulations on Safety and Protection of Radioisotope and Ray-generating Installations. It lays outthat the previous by-stage, multi-sector regulatory approach was changed to a unified regulatory
system by the environmental protection competent authority of radioactive sources. In 2002, theBasic Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources(GB18871-2002), a Chinese Standards, was issued.

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Control in RI facilities
2.1.1 Radiation Safety Control System
In 2005, the State Council issued the Regulations on the Safety and Protection ofRadioisotopes and Ray-generating Installations (the State Council Order No. 449). These
regulations, fully observing requirements stated in the IAEA Code of Conduct on the Safety andSecurity of Radioactive Sources and the Basic Safety Standards on Ionizing Radiation Protection

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and radioactive Sources(Chinese Standards GB18871-2002), have constructed a spectrum of
regulation mechanism. These include:a) Practicing a licensing system abided by organizations producing, selling, orusing radioactive sources;b) Full-traced control over applications of radioactive sources;c) Reviewing and documentation of radiation-related transfer, export and import;d) Documentation of sources applications in different locations from originallyassigned places;e) Specifying the procedures of retrieving disused radioactive sources tomanufacturers.
MEP(NNSA) supervises and administers the safety and security of radioisotope andradioactive equipments throughout the country in centralized manner, including the practicing andmonitoring of foresaid systems, construction of information system for monitoring and controllingradioactive sources, management of training radiation workers and monitoring dose
information to persons exposed to radiation, response to emergencies, and inspection of radiation
safety and security.
MEP(NNSA) takes direct responsibilities of reviewing, approving and granting licenses for
Category sources.
The provincial government authorities take responsibilities for the rest categories ofradioactive sources.
For local environment authorities (at level of city or county), special offices or technicians are
assigned to control and manage the applications of nuclear technologies within their jurisdiction.
MEP(NNSA) is responsible for establishing an information management system regarding the
production and use of radioisotope. Since 2004, MEP(NNSA) has commenced to localize IAEA’s
Radioactive Source Information System(RAIS), and now this system has been put into operation
throughout China.
2.1.2 Radiation Protection of Workers
In accordance with China’s laws and regulations, those organizations which produce, sell or
use radioisotope and radioactive equipments shall monitor radiation dose exposed to those staffs
who directly involves in activities of producing, selling or using those radioactive isotopes ordevices , and give the staffs occupational physical examinations, establish files of personalradiation dose and occupational health caring.
As regulator, the environmental protection authority is free from involving in tasks ofmonitoring personal radiation dose, nevertheless, the licensed organizations are required to filepersonal radiation dose documents and give an annual report to authorities granting the license. By
this mean, the authorities will be promptly informed with that if the safety and protection ofradiation work sites meets the requirements.
2.1.3 Radiation Protection of Working Area
According to China’s regulation, obvious radioactive sign should be set at the workplace inwhich radioisotope or ray-generating installations are produced, sold, used or stored, the radiation
protection facilities, necessary safety interlock and alarming devices should be set up at theentrance. Safety measures to prevent mis-operating and unexpected radiation exposure for theemployee or the public should be taken.

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The requirements for the monitoring of the workplace are consistent with the IAEA BSS in
China. Program for the monitoring of the workplace under supervision should be established,
maintained and kept. The nature and frequency of monitoring workplace should be determinedaccording to the radiation level and the potential exposures, to enable: i) evaluation of theradiological conditions in all workplace; ii) exposure assessment in controlled areas andsupervised areas and iii) review of the classification of controlled and supervised areas. The
program for monitoring of the workplace shall specify: i) the quantities to be measured; ii) where
and when the measurements are to be made and at what frequency; iii) the most appropriate
measurement methods and procedures; iiii) reference level and the actions to be taken if they areexceeded.
2.1.4 Public Radiation Protection
In China, The dose limits required by the standards for public exposure is as the followings:
1) An effective dose of 1 mSv in a year;
2) In special circumstances, an effective dose of up to 5 mSv in a single year provided thatthe average dose over five consecutive years dose not exceed 1 mSv per year;
3) An equivalent dose to the lens of the eye of 15 mSv in a year;
4) An equivalent dose to the skin of 50 mSv in a year.
The registrants and the licensees are responsible for any public exposure which is deliveredby the practice or source. The responsibilities are as the followings:
1) To establish protection and safety policies and organizational arrangements in relation to
public exposure in fulfillment of the requirements of the standards;
2) Take measures to ensure the optimization of the protection of members of the public, andthe limitation of normal exposure of the relevant critical group, which is attributable tosuch sources, in order that the total exposure be not higher than the dose limits formember of the public;3) To ensure the safety of such sources, in order that the likelihood of public exposure becontrolled in accordance with the requirements of the Standards;
4) To provide suitable and adequate facilities, equipments and services for the protection of
the public;5) To provide appropriate protection and safety training to personnel having functions
relevant to the protection of the public;6) To provide appropriate monitoring equipment and surveillance programmes to assess
public exposure ;7) To keep adequate records of the surveillance and monitoring ;8) To establish emergency plans or procedures;
9) To ensure the optimization process for measures to control the discharge of radioactive
substances from a source to the environment.
2.1.5 Emergency Action
According to the nature, severity, controllability and impact extent of a radiation accident, they
are classified into exceptionally serious radiological accidents, major radiological accidents,
serious radiological accidents and ordinary radiological accidents, with exceptionally serious
radiological accidents as the most serious and ordinary radiological accidents as the least.
The MEP is responsible for emergency response to radiation accidents, and for investigation

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and classification of the accident. For this reason, Radiation Accident Emergency Plan is speciallyestablished. Under the Council of State Decree 449, the environmental protection agencies of thepeople’s governments at or above county-level should work with the agencies responsible forpublic security, health and finance at the same level to make joint effort to prepare radiation
accident emergency plan within their own administrative areas. The plan is subject to approval ofcounty-level people’s governments to ensure their legality and validity and should make themavailable to the public in an appropriate form.
The license holder shall prepare emergency plan for its facility based on potential accident risk
and make emergency preparedness.
Once a radiation accident occurs, the holder of radiation safety license shall initiate emergency
plan that has been prepared in advance and take emergency measures to check the effectiveness ofthe measures taken from time to time. Within two hours after an accident occurring or being
discovered, report shall be made to the agencies responsible for the environment, health andpublic security. After receiving such a report, the agencies should dispatch personnel to theaccident site to conduct emergency fieldwork in a way consistent with the provisions, and at thesame time report the information to their respective upper level competent agencies in aprescribed way. The personnel that have arrived at the accident site should carry out their own
respective responsibility through taking effective measures, controlling and eliminating accidental
impacts. In the case of an exceptionally serious radiological accident or a major radiologicalaccident, the people’s governments at the level of province, autonomous region and municipality
directly under the State shall report to the State Council not later than 4 hours after the accident
occurs.
2.2 Radiation Safety Management in Nuclear Facility(Nuclear Power Plant, Research Reactor, Radioactive Waste Treatment Facility)
2.2.1 Radiation Safety Management System
A wide spectrum of laws, regulations and national standards are promulgated in China to ensure theachievement of the goals of radiation protection. On 8 June 2003, the Standing Committee of the
National People’s Congress promulgated the Law of the People’s Republic of China on Prevention andControl of Radioactive Pollution, laying down prevention and control of radioactive pollution as
follows:
1) The operator of a nuclear facility shall be responsible for the prevention and control ofradioactive pollution arising from such a facility and subject to the regulatory control of thecompetent authority of environmental protection and other relevant agencies, and take theliability of radioactive pollution arising from such a facility;2) The operator of any nuclear facility shall monitor the types and concentrations of radionuclides
in the surrounding environment and the quantity of radionuclides in effluents from such afacility, and report the monitoring results to the competent authorities of environmental
protection both under the State Council and at the provincial level;3) The operator of any nuclear facility shall make the effort to reduce the radioactive waste
generation as low as reasonably achievable. Release of gaseous and liquid radioactive wastes
into the environment shall be consistent with national standards on radioactive pollution
prevention and control, and the quantitative results of release shall be reported to the competentauthorities of environmental protection.

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Any nuclear facility is required to set dose limits as management goals under the GB18871-2002
taking account of economic and social factors, which should be lower than the relevant national limits.
The GB18871-2002 requires that release of radioactive materials into the environment shall becontrolled in such a way to determine the important pathways through which the public are exposed toradioactive material and that the impacts upon the human and the public shall be assessed. The
GB18871-2002 also sets up the following individual dose limits:-------Occupational exposure(1) Effective dose of 20 mSv per year is prescribed by regulatory body, averaged over defined 5
year periods, rather than any traceable average;(2) The effective dose should not exceed 50 mSv in any single year;(3) Annual equivalent dose for Lens of the eye is 150 mSv;
(4) Annual equivalent dose for hands and fee is 500 mSv;-------Public exposure(1) Annual effective dose limit is 1 mSv(2) In special circumstances a higher effective dose value of 5 mSv could be allowed in a single
year, provided that the average over defined 5-year periods does not exceed 1 mSv per year;(3) Annual equivalent dose for lens of the eye is 15 mSv;
(4) Annual equivalent dose for skin is 50 mSv.
2.2.2 Radiological Protection for Radiation Worker
According to the monitoring results of occupational exposures, the average annual dose equivalent
to workers in the operating NPPs in China is far below the national limits given in standards, as shownin the following Table 1.

38

FNCA Consolidated Report on Radiation Safety (China)

NPP

Year

2007
2008
2009
Guangdong
2007
Daya Bay NPP
2008
2009
Qinshan Phase 2007
II NPP
2008
2009
Guangdong
2007
LingAo NPP
2008
2009
Qinshan Phase 2007
III NPP
2008
2009
Tianwan NPP
2007
2008
2009
Qinshan NPP

Annualaverageindividual
effective dose（mSv）

Annualmaximum
individual
effective dose（mSv）

Annual collective
effective dose
（Man.Sv）

Normalized
collective
effective dose
（Man.mSv/G
Wh）

0.650
0.153
0.336
0.378
0.307
0.278
0.347
0.300
0.345
0.456
0.600
0.502
0.277
0.364
0.327
0.136
0.209
0.244

8.450
3.577
4.257
9.476
5.988
5.240
8.164
4.881
7.899
8.533
12.16910.568
5.900
9.102
6.415
2.693
3.460
3.200

0.997
0.149
0.453
1.053
0.826
0.715
0.785
0.588
0.710
1.231
1.772
1.531
0.572
0.788
0.748
0.327
0.557
0.548

0.450
0.057
0.192
0.068
0.051
0.044
0.088
0.059
0.071
0.083
0.116
0.099
0.050
0.070
0.064
0.033
0.040
0.038

Table 1: Monitoring results of occupational exposures

2.2.3 Radiation Area Management
Principles and requirements of radiation protection were provided for by national nuclear safety
regulatory bodies in a wide spectrum of regulations governing the siting, design and operation of
nuclear facilities at any stages:
1) At the stage of siting, the public and the environment should be protected from excess radiation
exposure from emerging radioactive accidents, simultaneously with due account being taken of
normal release of radioactive materials from NPPs;
2) Full consideration should be given to radiation protection requirements, such as optimized
facility deployment, installation shielding, in such a way to make the activities and occupancy
time of persons within radiation areas as less as possible;
3) Taking necessary measures to reduce quantity and concentrations of radioactive materials
within plant area or released to the environment;
4) Taking into careful consideration possible accumulation of radiation level with time within
occupancy area in such a way as to as less radioactive waste as possible to be generated;
5) Carrying out, on the part of operating nuclear facilities, assessment and analysis of radiation
protection requirements and their implementation, making and implementing radiation
protection programs to ensure the implementation of such programs and the verification of theirgoal achievement, and if necessary taking necessary corrective actions; and39

FNCA Consolidated Report on Radiation Safety (China)6) Making and implementing, by radiation protection functional departments, radioactive waste
management programs and environmental monitoring program to assess environmental
impacts of radioactive release.
The Technical Policies Governing Several Important Safety Problems in Design of Newly Built
NPPs was issued in August 2002, where nuclear safety analysis should be accomplished in designing
NPPs to assess the possible doses to both NPP’s workers and the public and potential environmental
consequences. Various measures are required to be taken for controlling radiation exposure and reduce
possibility of an accident.
2.2.4 Radiation Protection for Public
The Regulations on Radiation Protection for NPPs GB6249-86, clearly sets out effective dose
equivalent to any adult individuals of the public arising from released radioactive materials into theenvironment from NPPs and the annual release limits of airborne and liquid radioactive effluents:
1) Effective dose equivalent to any adult individuals of the public arising from a NPP should beless than 0.25 mSv;
2) In addition to meeting the above provisions, the airborne and liquid radioactive effluent from a
PWR NPP should be also less than the control values listed in the following Table 2.
Table 2: Annual discharge limits under operational conditions of a PWR Nuclear Power Plant (Bq)

Airborne radioactive effluent
Noble gas
IodineParticle(half-life≥8d)
15

2.5×1010

7.5×1011

2.0×10Liquid radioactive effluent
Tritiumother14

1.5×1011

7.5×10

Monitoring was made in the surrounding environment in provinces where China’ NPPs are located.
The results show that the discharged quantities of effluents in operational NPPs caused the maximum
individual doses to the public in the proximity far lower than national limits.
Environmental monitoring program was developed by nuclear facilities for key nuclides, exposure
pathways (transfer) and key populations as defined in the environmental impact report with a view tocarrying out environmental radioactivity monitoring to ensure compliance with the provision of therelevant national laws and regulations, satisfaction with radioactive waste discharge limits andprotection of the public from radiation impacts arising from nuclear facility operation. Environmental
radioactive monitoring data shall be used to assess and analyze the validity of controlling radioactive
material release into the environment, the public exposure from nuclear facility’ effluent, long term
trend in variation in environmental radioactivity, migration and dispersion of radioactive material in theenvironmental media and the reality of environmental model used for establishing authorized limits.
Environmental radioactive monitoring includes pre-operation monitoring, routine environmental
radiation monitoring, radioactive effluent monitoring and meteorological monitoring.
Pre-operation monitoring means a two-year long survey of radioactive background and ocean
ecology through which the information on key nuclides, key exposure (transfer) pathway and key
populations can be obtained. The investigated media comprise air, surface water, groundwater,terrestrial and marine organisms, foods, soils among other things. Environmental gamma radiation levelis investigated within 50 km of the proposed sites with others within 20 km of the proposed sites. Whatto be analyzed and measured includes environmental radiation level and radionuclides released from40

FNCA Consolidated Report on Radiation Safety (China)

nuclear facilities. Before operation of NPPs in China, environmental radioactivity backgrounds aremeasured and the results preserved in such a manner as to ensure the representative of environmental
monitoring extent and frequency that meet the relevant requirements.
Routine environmental radiation monitoring means that as much optimization as possible isachieved by nuclear facilities through making full use of pre-operation survey information on thepremise to meet the needs of environmental assessment. Environmental monitoring focuses on what isdeemed to be maximum risks to the key populations.
Radioactive effluent monitoring refers to the monitoring of gaseous and liquid radioactive effluents
after nuclear facilities come into operation, involving total quantity and concentrations of nuclides
released and the main nuclides to be analyzed. Monitoring results show that the quantity of radioactive
effluents discharged is not in excess of national limits.
Meteorological monitoring aims to atmosphere diffusion monitoring. Meteorological monitoring
programs have been prepared with the aim of making continuous monitoring of wind direction, velocity
and air temperature, precipitation and air pressure at varying heights above ground at the typicalselected locations. In addition, lines of communication are established between NPPs withmeteorological observatory stations in provinces where they are situated so as to obtain the needed
meteorological data.
Accident emergency monitoring means the environmental emergency plan prepared by NPPs prior
to their operation, where derived intervention levels are provided for in order to assess monitoring
results and decide whether or not to take necessary action as early as possible.
NPPs are equipped with radiation monitoring meters, radiation surveillance meters, contamination
monitoring meters, air sampler and environmental media sampler among others, with regular test andcalibration. All emergency equipment is, as required, tested for reliable use.
Assessment of public dose and environmental impact is performed at NPPs based environmental
monitoring data. Accumulated gamma radiation monitoring data at the plant boundary are used,
together with data in respects of atmosphere fly dust, terrestrial organisms, soils, water quality and otherenvironmental media, to assess the dose equivalent to the public and environmental impact arising fromthe operation of NPPs under normal and abnormal conditions
Effective environmental monitoring and assessment have been completed by NPPs under the
auspices of NNSA. The measurement and analysis of samples from biology, air, soils and ocean in thesurrounding environment show that NPPs have caused no adverse impacts on the environment.
2.2.5 Nuclear Emergency Response
Three-level emergency organizational system which has been established in China, which
consists of national nuclear emergency organization, provincial emergency organizations(including autonomous region, municipality directly under central government where nuclear
facilities are located) and the nuclear facility’s emergency organizations.
National Nuclear Accident Emergency Coordination Committee (NNAECC) organizes andcoordinates the country-wide nuclear emergency management arrangement. National Nuclear
Accident Emergency Office (NNAEO) is the management body for country-wide nuclear accident
emergency arrangements
If necessary, the State Council shall lead, organize and coordinate country-wide nuclear
accident emergency arrangements.
The MEP (NNSA) executes independent supervision of NPPs’ nuclear accident emergency
arrangements, and overseeing the development and implementation of NPP nuclear accident

41

FNCA Consolidated Report on Radiation Safety (China)

emergency plan.
The competent authorities of environmental protection, health, army and other related
agencies shall make every effort to implement nuclear accident emergency response arrangement
within the scope of their responsibilities.
Nuclear accident emergency committees of provincial governments where nuclear facilities
are located are responsible for nuclear accident emergency arrangements within theiradministrative areas.
Nuclear accident emergency organizations of nuclear facilities have the following
responsibilities:
1) Enforcing national regulations and policies on nuclear accident emergency arrangements;
2) Preparing onsite nuclear accident emergency plan and making nuclear accident emergency
arrangements;
3) Determining nuclear accident emergency classification, commanding nuclear accident
emergency response actions;4) Timely notifying information on nuclear accident situation to the higher competentauthorities, the MEP (NNSA) and the agencies designated by provincial governments andmaking suggestions on initiating off-site emergency actions and protective actions; and5) Assisting and helping the agencies designated by provincial governments in making
nuclear accident emergency arrangements.
The following four emergency classes are used in China, in order of increasing severity.
1) Emergency standby: Certain types of special conditions and external events that could
endanger the safety of nuclear facilities are expected to have occurred. Nuclear facility
emergency personnel are in standby and some of the offsite emergency organization may
be notified;2) Plant emergency: Radiation consequences is only limited to part of in-plant area. In thiscase, onsite personnel may take actions under emergency plan and relevant offsite
emergency organizations may be notified;3) Plant area emergency: Radiation consequences are only limited to in-plant area. In thiscase, onsite personnel put into action and offsite emergency organization may receive
notifications, also with some have potential to take actions; and
4) Offsite emergency: Radiation consequences are expected to have exceeded plant boundary.
Onsite and offsite personnel start to take actions, and onsite and offsite emergency plans
start up.
When in the emergency standby situation, emergency organization of a nuclear facility shalltimely report to higher competent department and MEP (NNSA) and to nuclear accident
emergency committee of the province where such nuclear facility is located where appropriate.
When any releases of materials are expected to be in process or have occurred, plant emergency orplant area emergency shall be initiated timely where appropriate and shall report to the higher
competent department, the MEP (NNSA) and provincial accident emergency committee.
When radioactive materials are expected to be in process or have dispersed to outside the plantarea, suggestions shall be made on entering into plant area emergency situation and taking
protection actions. After receiving notification on accident, provincial nuclear accident emergency
committee shall take emergency countermeasures and prompt actions and report timely to national

42

FNCA Consolidated Report on Radiation Safety (China)

nuclear accident emergency committee. Determination to enter into offsite emergency situation is
subject to approval from the NNAECC. In some special conditions, provincial nuclear accident
emergency committee can determine to enter into offsite emergency situations prior to approval
and then report timely to the NNAECC.
When entering into an offsite emergency situation, the NNAEO, MEP (NNSA) and otheragencies involved shall dispatch persons in a timely manner to the field and provide guidance tothe nuclear emergency response actions.

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FNCA Consolidated Report on Radiation Safety (Indonesia)

4. Indonesia
Part 2. Status of Radiation Safety Management ................................................................. 45
2.1 Radiation safety management in Radioactive Waste Management ................................ 45
2.1.1 Radiation Safety Management System .................................................................... 45
2.1.2 Radiation Safety Survrilliance ................................................................................ 45
2.1.2.1 Area Monitoring ............................................................................................. 45
2.1.2.2 Personnel Monitoring ..................................................................................... 46
2.1.2.3 Effluent Monitoring ........................................................................................ 46
2.1.2.4 Monitoring Public Exposure............................................................................ 46
2.1.2.5 Environmental Monitoring .............................................................................. 46
2.1.2.6 Emergency Preparedness ................................................................................ 46

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FNCA Consolidated Report on Radiation Safety (Indonesia)

4. Indonesia
Part 2. Status of Radiation Safety Management
2.1 Radiation safety management in Radioactive Waste Management
2.1.1 Radiation Safety Management System
Radioactive waste management technology center (RWMTC) at BATAN Serpong is
responsible on managing any kinds of radioactive wastes generated by all radiation and nuclear
facilities in Indonesia. In Serpong, the wastes mostly come from research reactor, chemical
processing facilities including radioisotope and radiopharmacy production facilities, and fuelelement and radiological laboratories.
Radioactive waste management technology center (RWMTC) is a centralized facility at
Serpong site for solid and liquid waste treatment. Solid radioactive wastes collected in standard
100 liter drums from the different source are brought to RWMTC at Serpong site. They aresegregated into combustible and non-combustible, and compressible and non-compressible types.
The low active combustible wastes are incinerated and the compressible ones are compacted in
200 liter drums. Non-combustible and non-compressible wastes are packed into 200 liter concrete
drums and stored in an interim storage. Liquid waste transported from generating facility to
RWMTC through mobile tank for evaporation and/or chemical treatment. Sludge generating from
evaporation or chemical chemical treatment and ash from incineration treatment are cemented in
200 liter standard drums. Liquid radioative effluent below clearance levels is discharged to
Cisalak river.
2.1.2 Radiation Safety Survrilliance
RWMTC is designed to provide adequate radiological safety for operating staff, members of
the public and the environment. Contamination control is applied by zoning policy, and suitable
protective clothing is provided at appropriate locations. Liquid effluent generated from facility
operation is discharged by pipelines through integrated waste control (IWC/PBT). Ventilation
system is also designed so that the facility areas are kept under negative pressure. The exhaust air
is discharged to atmosphere through a bank of high efficiency particulate air (HEPA) filters.
2.1.2.1 Area Monitoring
The radiation fields of all working areas including those outside the waste processing facility
are monitored routinely. Working areas are also checked for radioactive contamination by swiping(smear tests), with special attention given to areas like corridors, worker rooms, etc. Location
where radiation field is excessive are identified and classified. Adequate shielding is provided forequipments which show high dose rates. Occupancy in high radiation field areas is controlled by
the system of special work permit (SWP). Area radiation monitors with alarm setting are installedat few locations in the facilities. A routine air sampling programme is in place, employing
discontinuously operated air samplers at fixed location, and by batch air samplers during routine
and specific operations.

45

FNCA Consolidated Report on Radiation Safety (Indonesia)

2.1.2.2 Personnel Monitoring
Personnel monitoring for external exposure is routinely carried out using thermo luminescentdosimeters (TLD). In addition, digital personnel dosimeters are used for immediate assessment ofradiation dose. Average exposure per worker in 2009 is less than 5,0 % of the national annual dose
limit, and the maximum individual annual dose around 8.5 % of this limit, i.e. 20 mSv.
Monitoring for internal contamination to radiation workers at Serpong Nuclear Area arecarried out through bioassay and in-vivo counting. Bioassay by urine analysis is carried out once a
year as routine, and more frequently in case of suspected internal contamination. In-vivo counting,for estimation of gamma radionuclides is carried out for certain workers potentially expectedcontaminated, has revealed no occurences of internal contamination in 2009 at Serpong.
2.1.2.3 Effluent Monitoring
Liquid effluent from Serpong Nuclear Facilities is collected in a pond and released by
RWMTC. Before discharging through river, the liquid effluent is analyzed to determine
radionuclide concentrations and their chemical and physical forms, and then compared with theappropriate environmental radioactivity level standards. Environmental monitoring carried out
every 3 months on Cisadane river. Analysis results of effluent samples has revealed that 60Co and65
Zn in the liquid effluent. Most of the effluent is generated by the Serpong Research Reactor.
2.1.2.4 Monitoring Public Exposure
Surface water from Cisadane river and other environmental components are regularly
monitored for their radioactivity concentration. Estimated maximum possible radiation exposureof member of public due to consumption of foodstuff and occupancy of bank areas (critical group),
is estimated to be negligibly low when compared to recommended annual dose constraint of 300
Sv for public. Monitoring results showed that there was no increase in radiation dose in theenvironment, only the background radiation dose from terrestrial exposure and cosmic ray.
2.1.2.5 Environmental Monitoring
Monitoring of environment around the facility is carried out by background radiation survey,
and analysis of ground water and surface soil samples. Any abnormal increase in radiation field isinvestigated for its causes, and corrective actions taken. Samples of ground water and surface soil
from around RWMTC are collected with a defined periodicity and analyzed for radionuclide
quantification.
2.1.2.6 Emergency Preparedness
RWMTC is part of the Serpong Nuclear Area Emergency Preparedness and Response
Arrangements, so that the emergency preparedness refers to emergency preparedness programmesof Serpong Nuclear Area.

46

FNCA Consolidated Report on Radiation Safety (Japan)

5. JapanPart 1. Radiation Safety in RI Facilities.... エラー! ブックマークが定義されていません。
1.1 General........................................... エラー! ブックマークが定義されていません。
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1.3.4 Recent Movement Concerning Radioisotope Sourcesエラー! ブックマークが定義されていません。
1.4 Education and Training .................... エラー! ブックマークが定義されていません。
1.4.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc.エラー!
ブックマークが定義されていません。
1.4.2 The Nuclear Reactor and Fuel Law エラー! ブックマークが定義されていません。
1.4.3 The Labor Standards Law ............. エラー! ブックマークが定義されていません。
1.4.4 Examples of Education and Trainingエラー! ブックマークが定義されていません。
1.5 Standardization on Radiation and Radioactivityエラー! ブックマークが定義されていません。
Part 2. Status of Radiation Safety Managementエラー! ブックマークが定義されていません。
2.1 Radiation Safety Control in RI facilitiesエラー! ブックマークが定義されていません。
2.1.1 Radiation Safety Control System ... エラー! ブックマークが定義されていません。
2.1.2 Radiation Protection of Worker ...... エラー! ブックマークが定義されていません。
2.1.3 Radiation Protection at Work Area . エラー! ブックマークが定義されていません。
2.1.4 Radiation Protection of the Public .. エラー! ブックマークが定義されていません。
2.1.5 Radiation Emergency Response..... エラー! ブックマークが定義されていません。
2.2 Radiation safety management in Research Reactorsエラー! ブックマークが定義されていません。
2.2.1 Radiation Safety Management Systemエラー! ブックマークが定義されていません。
2.2.2 Radiation Protection for Radiation Workerエラー! ブックマークが定義されていません。
2.2.3 Radiological Protection for Radiation Areaエラー! ブックマークが定義されていません。
2.2.4 Radiological Protection for the Publicエラー! ブックマークが定義されていません。
2.2.5 Radiation Emergency Preparedness エラー! ブックマークが定義されていません。
2. 3 Radiation Management in Nuclear Power Plantsエラー! ブックマークが定義されていません。
2.3.1 Radiation Safety Management Systemエラー! ブックマークが定義されていません。
2.3.2 Radiological Protection for Radiation Workerエラー! ブックマークが定義されてい47

FNCA Consolidated Report on Radiation Safety (Japan)ません。
2.3.3 Radiation Area Management ......... エラー! ブックマークが定義されていません。
2.3.4 Radiological Protection for the Publicエラー! ブックマークが定義されていません。
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クが定義されていません。
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2.4.2 Radioactive Waste Management in the Research Facilitiesエラー! ブックマークが定義されていません。

48

FNCA Consolidated Report on Radiation Safety (Japan)

5. JapanPart 1. Radiation Safety in RI Facilities
1.1 General
1.1.1 Legislative and Regulatory Framework
The basic law on the utilization of nuclear energy in Japan is the Atomic Energy Basic
Law (AEBL) that was established in 1955. The objectives of the law are quoted as “to secure
future energy resources, achieve progress in science and technology, and promote industry, by
encouraging research, development, and utilization of nuclear energy, and thereby contributeto the improvement of the welfare of human society and the national living standard.” Thebasic policy here is prescribed as follows: “The research, development and utilization of
nuclear energy shall be limited to peaceful purposes, on a basis of ensuring priority to safety,
and performed on a self-disciplined basis under democratic administration, and the results
thereof shall be made public and actively contribute to international cooperation.”
In order to attain these objectives and achieve the basic policy, the law prescribes
the following:- Establishment of the Atomic Energy Commission (AEC) and the Nuclear Safety
Commission (NSC), and their duties, organization, administration, and authorities- Regulations on the nuclear fuel materials- Regulations on the construction, etc. of reactor facility.
- Prevention of radiation hazards
The law also prescribes the assignment of these matters to the respective laws. Major laws
established for the purpose of providing safety regulations on the utilization of nuclear energy
and related laws include “the Law for the Regulation of Nuclear Source Material”, Nuclear
Fuel Material and Reactors (the Reactor Regulation Law)”, “the Electricity Utilities Industry
Law”, “the Law Concerning Prevention from Radiation Hazards due to Radioisotopes, etc.
(the Radiation Hazards Prevention Law)” and “Medical Care Law”, etc. Also included are“the Basic Law for General Emergency Preparedness,” “the Special Law of Nuclear
Emergency Preparedness (the Special Law for Nuclear Emergency),” “the Law for TechnicalStandards of Radiation Hazards Prevention” and “the Specified Radioactive Waste Final
Disposal Act,” etc.
1.2 Regulatory body
The mandate of the regulatory bodies is to ensure public safety through securing safety of
nuclear facilities, and their obligations are to implement the above-described legislative andregulatory framework. The regulatory bodies are responsible for conducting regulatory
activities prescribed in the Reactor Regulation Law, the Radiation Hazards Prevention Law,etc. on the basis of the Atomic Energy Basic Law. Their organizations and assigned
obligations are clearly defined in their respective establishment laws, and their financial
resources are covered by the national budget.
The Minister of Economy Trade and Industry (METI) serves as the competent minister49

FNCA Consolidated Report on Radiation Safety (Japan)

for safety regulation on activities concerning utilization of nuclear energy, and Nuclear andIndustrial Safety Agency (NISA) administers the regulatory activities as a special organization
for METI. The Minister of Ministry of Education, Culture, Sports, Science and Technology(MEXT) serves as the competent minister for the safety regulation over the nuclear utilization
associated with science and technology and the utilization of radioisotopes (except medicines,etc.), etc., and the Science and Technology Policy Bureau (STPB) administers the regulatory
activities. The Minister of Ministry of Health, Labor and Welfare (MHLW) governs the safety
regulation concerning medical facilities as the competent minister, and the Pharmaceuticaland Food Safety Bureau (PFSB) and the Health Policy Bureau (HPB) administer the
regulatory activities.
Regulatory bodyNISA (Nuclear andIndustrial Safety Agency) /METI (Minister of
Economy Trade andIndustry)
STPB (Science andTechnology Policy
Bureau), MEXT (Ministryof Education, Culture,
Sports, Science andTechnology)
HPB (Health Policy
Bureau) and PFSB
(Pharmaceutical and Food
Safety Bureau), MHLW(Ministry of Health, Laborand Welfare)

Assigned Facilities and Activities
Activities for utilization of nuclear energy.
Namely, nuclear power reactor facilities and related
nuclear fuel cycle facilities

Utilization of nuclear power for science andtechnology, and utilization of radioisotopes etc.
(except for medical supplies etc.). Namely, test andresearch reactor facilities, facilities handlingradioisotopes, etc.
Activities at facilities for medical treatment andmedical cares. Namely, manufacturing, handling,storage and disposal of radiopharmaceuticals.

Table 1: Regulatory bodies and Assigned Facilities and Activities

These regulatory bodies have clearly defined duties on safety regulation, and their
independence is ensured both in legislation and in substance.
The NSC, consisting of members whom the Prime Minister appoints with consent of theDiet, observes and audits activities of these regulatory bodies (Regulatory Review), andestablishes the basic policy for safety regulations therefore the consistency among theregulations is maintained. The consistency of the technical standards for prevention ofradiation hazard is discussed at the Radiation Review Council under the MEXT.
Reference: Government of Japan, Joint Convention on the Safety of Spent Fuel Management and on
the Safety of Radioactive Waste Management, National Report of Japan for the Second Review
Meeting Oct. 2005.

50

FNCA Consolidated Report on Radiation Safety (Japan)

1.3 Outline of Radiation Facilities and Radiation Sources
Laws and Ordinances apply uniformly regardless of the nature of the establishment. It isappropriate to think of them as stipulating the minimum standards that the establishments andthe radiation workers should observe, and, accordingly, each establishment, while of course
meeting the legally prescribed standards, should implement radiation control appropriate forits own activities.
The Law Concerning Prevention of Radiation Hazards was drafted and modified in linewith recommendations of the ICRP, its provisions on radiation control are not significantly
different from those in other countries.
The purpose of the Law Concerning Prevention of Radiation Hazards is to prevent
radiation hazards to radiation workers and the public and to protect the environment whenradiation or radioisotopes are used. In order to attain this purpose, the Law provides for the
regulation of facilities (requirement for facilities) and for the regulation of people’s actions,etc. (for requirement for actions).
1.3.1 Authorization
Prior to the use of radiation or radioisotopes, permission by or notification to the Ministerof Education, Culture, Sports, Science and Technology (MEXT) is required.
(1) Permission: The use of generators, unsealed radioisotope sources and sealed radioisotope
sources more than 1,000 times of the lower Activity Limits. The disposal ofradioisotope wastes.
(2) Notification: The use of sealed radioisotope sources less than 1,000 times of the lower
Activity Limits. The sale of radioisotope sources.
(3) Notification of Certification Equipments: The use of ECD, etc. which receive the design
certification beforehand.
The number of users by category of organizations permitted by and notified to MEXT
since 1959 when the Law was enforced is shown in Fig.1.
The use of radiopharmaceuticals is regulated by the Medical Service Law. The number ofusers of radiopharmaceuticals is shown in Table 2.
Fig.1: Number of users by category of organizations permitted by and notified to MEXT

(Number of users: Total)

51

FNCA Consolidated Report on Radiation Safety (Japan)

Table 2: Number of licensed hospitals and clinics for using radiopharmaceuticals

1.3.2 Workers and Specialists in Radiation Facilities
1.3.2.1 Radiation Workers
Those who are given permission to use, or who submit a notification on the use ofradioisotopes or radiation, must comply with a series of standards for safety control, in orderto prevent radiation hazards.
Specific standard apply to workers who enter controlled areas: Education and training,measurements of personal dose and medical examinations. The round number of radiation
workers including x-ray device handlers is shown in Table3.
Table 3: Round number of radiation workers(including x-ray device handlers, 2009)

1.3.2.2 Radiation Protection Supervisors
In order to conduct appropriate and thorough radiation safety control at an establishment,
it is necessary to have a management structure or mechanism in place that is responsible forradiation protection control within the establishment. In such a situation, the radiation
protection supervisor is playing the key role. Radiation protection supervisors are people
responsible for supervising efforts to prevent radiation hazards. They are appointed at any
establishment where radiation or radioisotopes are handled in the course of using, selling,leasing, or disposing of them.
To be qualified as a radiation protection supervisor, a person must complete required
training courses and pass a national examination. There are three classes of radiation
protection supervisors – first class to third class. Which class is required by a particularestablishment depends on the kind and level of radiation or radioisotopes handled. Moreover,
Radiation protection supervisors must attend seminars, etc., an on-going basis, in order toalways have the latest information in the field of radiation protection.
Contents of the National Examinations and the Regulatory Training Courses for radiation
protection supervisors are shown in Tables 4 and 5 respectively. The National Examinations

52

FNCA Consolidated Report on Radiation Safety (Japan)

for radiation protection supervisors (first class) is shown in Fig. 2.
Table 4: National examination for radiation protection supervisor

Table 5: Regulatory training course for radiation protection supervisor(Number of examinees and successful applicant)(Ratio of successful applicants)

Fig.2: National examinations for radiation protection supervisors (First class)1.3.3 Activity of Radiation Sources and Number of generators
Amounts of major unsealed radioisotopes, major sealed radioisotopes and major

53

FNCA Consolidated Report on Radiation Safety (Japan)

radiopharmaceuticals, distributed by Japan Radioisotope Association are shown in Figs. 3, 4
and 5 respectively. Number of radiation generators given permission to use by MEXT isshown in Table 6.
(GBq)(GBq:Total)

700

4,000

600

3,500
3,000

500

Tota l
H -3
C-14

2,500
400

P-32
2,000

300
1,500
200
100
0
2005

2006

2007

Mo-99

500

I-125

2008

Fig.3: Amounts of major unsealed radioisotopes distributed by JRIA

(GBq: I-125, Kr-85)(TBq: Ir-192, Cs-137)( PBq: Co-60, Total)

Fig4: Amounts of major sealed radioisotopes distributed by JRIA

54

Kr-85

1,000

0
2004

S-35

FNCA Consolidated Report on Radiation Safety (Japan)(TBq)(TBq:Total)

350

580

300

570

Total

250

560

F-18

200

550

150

540

Tc-99m(G)Tc-99m
I-123

100

530

50

520

I-131
Tl-201

510

0
2004

2005

2006

2007

2008

Fig.5: Amounts of major radiopharmaceuticals distributed by JRIA

Table 6: Number of radiation generators permitted by MEXT

1.3.4 Recent Movement Concerning Radioisotope Sources
1.3.4.1 Sealed Radioisotope Sources Registration System
Registration of sealed radioisotope sources was tightened on the basis of the Law
Concerning Prevention of Radiation Hazards according to the Code of Conduct (IAEA).
On-line computer system for sealed sources registration was introduced and started operationin MEXT from 2009. Input of the more detailed information on sealed source was obliged to55

FNCA Consolidated Report on Radiation Safety (Japan)

make.
1.3.4.2 Disposal of Radioisotope Wastes
Facilities for disposal of radioactive wastes from the operation of the Nuclear Power
Plants were operated at Rokkasho site by Japan Nuclear Fuel Limited from 1992.
Implementing organization for disposal of radioisotope wastes from radioisotope utilization
decided to be Japan Atomic Energy Agency (JAEA). The disposal plan is covering allradioisotope waste from institutes, universities, hospitals, etc. Planning for the construction of
disposal facilities by JAEA is in progress.
1.3.4.3 Clearance Regulation of Radioisotope Wastes
Clearance regulation system already established with Nuclear Reactor Regulation Law by
the Ministry of Economy, Trade and Industry. The clearance regulation is applying to metal
and concrete arising from decommissioning of the Nuclear Power Plants. Some metalmaterials were already recycled according to the clearance regulation. On the other hand,
MEXT decided a similar clearance regulation system with the Law Concerning Prevention ofRadiation Hazards. This clearance regulation is applying widely not only to metal andconcrete but also to other solids arising from radioisotope utilization and activation by
generators. Amendment and enforcement of this clearance regulation is scheduled in 2010
and 2011, respectively.
1.4 Education and Training
1.4.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc.
Radiation users shall give radiation workers education and training, (1) prior to their firstentering in controlled areas; and (2) at least once a year thereafter (re-education). By there-education, radiation workers obtain the latest knowledge on regulations, radiation effects,
and techniques for safe handling, as well as have an opportunity to regularly reaffirm theimportance of safe handling.
Radiation users shall give inexperienced radiation workers shall give knowledge listed in
the Table 8, and minimum education time for each item is clearly determined by the law.
Sometimes OJT (on-the-job-training) or special curriculum of practical training is prepareddepending on the situation of radiation usage in each facility for more effective education.
Table 7 Items and minimum time on education and training for radiation workers, determinedby the Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc
Table 7: Items and minimum time on education and training for radiation workers, determined by the
Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc.

Items for education
Effects of radiation on human body
Safe handling of radioisotopes and radiation generators
Laws and ordinances on prevention of radiation hazards byradioisotopes and radiation generators
Local radiation protection rules in the facility
A: Radiation workers
B: Workers who do not enter controlled areas

56A
30 min
4 hrs
1 hr

B
30 min1.5 hrs
30 min30 min30 minFNCA Consolidated Report on Radiation Safety (Japan)

1.4.2 The Nuclear Reactor and Fuel Law
For users of special nuclear materials (SNM, defined by the law), users shall give theworkers additional education. The education items and frequency shall follow the local rule ofeach facility. The education items shall include;- Laws and ordinances on the Nuclear Reactor and Fuel Law- Structure of, specification of, and how to handle, the related facilities andinstruments- Radiation management- How to handle contaminated materials- Emergency action- Nuclear security including physical protection, etc.
Minimum time for this education item is not determined by the law.
1.4.3 The Labor Standards Law
When a new worker is employed, the employer shall give the worker education for safety
and his health concerning his work operations, following the Ordinance of the Ministry of
Health, Labor and Welfare. In addition, when a worker is to be involved in several special
operations designated by the Ordinance of the Ministry of Health, Labor and Welfare, theemployer shall give the worker the special education for safety and his health concerning therelated operations, following the Ordinance. Works on transparent photographs and movies
using X ray generators, and works in nuclear fuel facilities or nuclear reactors are included in
the special operations.
1.4.4 Examples of Education and Training
1.4.4.1 Nuclear Power Plant- Fundamental and practical knowledge (5 hours)
1) Nuclear fuel materials, spent fuel, or materials contaminated with them2) Works and operations in nuclear reactor facilities
3) Structure of, specification of, and how to handle, the related facilities and instruments
4) Effects of radiation on human body5) Laws and ordinances on the Nuclear Reactor and Fuel Law- Practical skills (2 hours)
1) Works and operations in nuclear reactor facilities and handling of equipment relating to
the facilities- Overall practical education (OJT) (10 days)
1.4.4.2 University (users of radioisotopes, accelerators, and X ray generators)- Knowledge of radioisotopes and their utilization (90 min)
- Laws and ordinances (2 hours)- Radiation measurements (60 min)- Effects of radiation on human body (60 min)- Local radiation protection rules in the facility (30min)- Practical trainings using radioisotopes with low activity (OJT) (3 hours)
1.5 Standardization on Radiation and Radioactivity
Radiation safety and radioactive waste management must be based on the reliable and57

FNCA Consolidated Report on Radiation Safety (Japan)

precise measurement of the quantities associated with ionizing radiation such as dose (Sv) andradioactivity (Bq). For radiation safety, various dose meters are being used such as electric or
passive dosimeters for personal dose and survey meters for ambient dose. Dose meters must
be calibrated regularly and always must show a right value in order to ensure the safety andsecurity of the people related to ionizing radiations. Measuring instruments such as ionizationchambers, scintillation counters and semiconductor detectors are important in radioactive waste
management, which need to be calibrated using reference radioisotope sources. Normallycalibrations are performed by calibration laboratories, where measuring devices are relatively
calibrated by reference instruments. These reference instruments are in turn calibrated byreference instruments with higher accuracy (lower uncertainty). The chains of the relative
calibrations never loop to avoid circular reference and end up to the reference instruments withhighest accuracy, called national standards. From the viewpoint of accuracy and reliability inmeasurement, it is essential to calibrate measuring instruments and secure the traceability ofmeasurement to national standards.
In Japan, national standards on ionizing radiation are maintained and provided at the
National Metrology Institute of Japan (NMIJ)1 in the National Institute of Advanced Industrial
Science and Technology (AIST). Table 1 shows the national standards on ionizing radiationand primary instruments used in absolute measurement of each quantity. Accuracy andworldwide consistency of the national standards were verified by participating about 100 times
in the international key comparisons organized by the Consultative Committee for Ionizing
Radiation (CCRI) of the International Committee of Weights and Measures (CIPM) in theInternational Bureau of Weights and Measures (BIPM) as well as the Technical Committee for
Ionizing Radiation (TCRI) in the Asia Pacific Metrology Program (APMP). The results ofthese comparisons are documented in the BIPM web page2. The national standards are being
operated with the quality management system conforming to ISO/IEC 17025 (General
requirements for the competence of testing and calibration laboratories) and peer-reviewed byexperts from major foreign national metrology institutes every four years. The calibration
certificates issued on these standards can be accepted worldwide within the range specified in
the Calibration and Measurement Capabilities (CMCs)3 in the framework of the CIPM Mutual
Recognition Arrangement (CIPM-MRA).
With regard to the traceability of measurement, the measurement act introduced the Japan
Calibration Service System (JCSS) in 1993, consisting of the national standards provisionsystem and the calibration laboratory accreditation system. In the national measurement
standards provision system, the Ministry of Economy, Trade and Industry (METI) designates
national primary standards and NMIJ calibrates the reference standards of accredited
calibration laboratories (i.e. secondary standards) with national primary standards. In thecalibration laboratory accreditation system, calibration laboratories are assessed andaccredited as accredited calibration laboratories to meet the requirements of the measurement
act, relevant regulations and ISO/IEC 17025. Calibration laboratories are also required tohttp://www.nmij.jp/english/
http://kcdb.bipm.org/AppendixB/
3 http://kcdb.bipm.org/AppendixC/
1
2

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FNCA Consolidated Report on Radiation Safety (Japan)

periodically take assessment as well as proficiency testing. Calibration certificates with a
JCSS symbol issued by accredited calibration laboratories assure the traceability to National
Measurement Standards as well as a laboratory's technical and operational competence andare acceptable in the world through the MRA of the International Laboratory Accreditation
Cooperation (ILAC) and the Asia Pacific Laboratory Accreditation Cooperation (APLAC).
Table 8: Quantities and primary standard instruments for the national standards
on ionizing radiation in Japan

Air kerma, Exposure (X, γ-ray)
10-50 kV (Low), 30-300 kV (Medium),
20-25 kV (Mammography): Free air ionization chamber
Co-60, Cs-137: Graphite wall cavity chamber
Absorbed dose (β-ray)
Sr-90/Y-90, Kr-85, Pm-147: Extrapolation chamber
Fluence (neutron)
Thermal: Gold foil activation
144 keV, 565 keV: Hydrogen proportional chamber
2.5 MeV, 5.0 MeV, 8.0 MeV: Thick radiator detector
14.8 MeV: Associate alpha particle counting
Am-Be, Cf: Standard Am-Be source
Emission rate (neutron)
Am-Be, Cf: Standard Am-Be source
Radioactivity, Emission rate (α,β,γ-ray)
Radioactive nuclides (74 species): 4πβ-γcoincidence counter

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Control in RI facilities
2.1.1 Radiation Safety Control System
There are about 4,900 RI facilities (research laboratories of universities and companies,
nuclear medical facilities etc.) in Japan.
These facilities are required to calculate whether dose in the controlled areas or within theboundary of the facility, concentrations of discharged air and liquid effluent from the facilities
are respectively lower than dose and concentration references. It is also required by the law tosubmit applications and documents to concerned government ministries before operating thefacility.
The facilities are required to record and check the measurements during practicaloperation using a radiation monitor such as gas monitor. Therefore, almost all RI facilities inJapan employ radiation control systems to simplify the management and automation of record
keeping.

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FNCA Consolidated Report on Radiation Safety (Japan)

The radiation safety control system is employed in combination with the following
systems in accordance with intended use.
a. Radiation Monitoring System (Fig.6)
The radiation monitoring system consists of an area monitor that monitors equivalentdose in a controlled area and a room gas monitor that monitors radioactive concentrationin the operating room. In addition, a gas monitor that monitors radioactive concentrationof gas discharged from facilities to the public, and a liquid monitor that monitors
radioactive concentration of effluent are part of the system.
Since the latest radiation monitoring system has been computerized, each monitor iscentrally controlled by the central monitor (computer) which automatically creates daily,
monthly and yearly reports, trend graphs of the alarm settings and measurement dataaccording to the control levels. (Fig.7).

Operation consoleFig.6: Configuration of Radiation Monitoring System

Fig.7: System Control Screen

b. RI Liquid Effluent Control System
The RI liquid effluent control system is installed to control discharged water from thosefacilities. The system automatically controls and remotely monitors storage, decay, anddilution of RI effluent.
By interfacing with the radiation monitoring system, many of those facilities perform
automated effluent sampling and control radioactive concentration in the effluent using aliquid monitor in accordance with the amount of water in storage tank.
c. Access Control System
The access control system automatically restricts access of qualified personnel thataccess to RI facilities and controls access records by ID card (magnetic/contactless smart
card FeliCa system ,etc.) or biometrics (fingerprint/vein matching) authentication.
Generally, the system only permits access of authorized personnel to the controlled areaof RI facilities. Accessible area or time can be selected for each qualified radiation worker
with the system.
At the time of exit from the controlled area, each radiation worker is checked with ahand-and-foot monitor and can exit the controlled area only if there is no contamination
detected.
The system is used in combination with limit switches of doors or key switches for60

FNCA Consolidated Report on Radiation Safety (Japan)

personnel access check in the facilities where interlocks are required and is also used as apart of an interlock system to prevent equipment from starting when radiation workers arein the specified areas of such as accelerator facilities.
The central monitoring system generates daily, monthly, and yearly reports as well as
displaying lists of workers who are currently in the controlled area.
Internal exposure evaluation of workers can be calculated by checking the data of
personnel working in controlled areas including their access times in the controlled area on
specified dates and times. In addition, contamination or a loss of radiation sources can be
determined with data traceability.
d. Unsealed Radioisotope Stock Control System
The unsealed radioisotope stock control system is mainly used in RI facilities because
the system unifies the management of procurement, acceptance, storage, utilization,
disposal and delivery of waste for unsealed radioisotopes in compliance with laws.
At the time of procurement or acceptance, the system easily checks that purchased or
accepted quantities are within regulated quantities (maximum quantities per day, 3 months
or year) for the storage and specifies by whom, when, and where each source is used andthe quantity of each used source. In addition, the residual quantity of sources and what
container the waste is in is checked, which allows the RI facility manager to easily
generate control reports in compliance with laws (Fig.8).
Recently, a stock check system using the RI stock list, noncontact IC tag and handy
terminal was introduced (Fig.9). The system is useful for daily source control as well as
periodic stock control because the system reduces the stock check time (check for loss ofstock).

Fig.9: Stock Control System

Fig.8: System Control Display

e. Personal Dose Control System
The purpose of the personal dose control system is to streamline the evaluation ofeffective dose at the facility. Measurements of personal dosemeters and the results ofperiodic health check-ups can be input into the system. By interfacing with the access
control system, workers who have not taken the periodic health check-up and those whohave exceeded the dose limit can be detected so as to prevent them from entering theaccess control area.
In addition, a personal dose control system utilizing an electronic dosemeter, which is61

FNCA Consolidated Report on Radiation Safety (Japan)

also used in the dose evaluation at nuclear power plant etc., has started to become widelyused.
2.1.2 Radiation Protection of Worker
Radiation Protection for the radiation work personnel is provided by the evaluation of
external exposure dose using personal dosemeter (It is measured and evaluated every monthwith glass badges and other method. It is generally outsourced.) and by the periodic healthcheck-up set forth by law, in order to check that the total amount of external and internal
exposure dose does not exceed yearly effective dose limit. However, these methods merely
check whether to have been exposed or not after the occurrence. It is important to emphasize
the radiation protective measures within work area for reduction of exposure more assertively.
Therefore, employment of aforementioned personal dose control system using theelectronic dosemeter is also effective so that plant manager can take appropriate measures bydetecting radiation exposure promptly.
2.1.3 Radiation Protection at Work Area
Environmental monitoring is conducted for radiation protection at work area by thefollowing methods. The monitoring is required to conduct in order not to exceed themonthly-base limit in compliance with laws and regulations. The monitoring is conducted by
Manager, but mostly it is outsourced.
2.1.3.1 Measurement of Airborne Radioactive Concentration
Airborne Radioactive Concentration is measured by filtering method with movable dust
sampler. It is for internal exposure evaluation of worker, and is implemented in a room where
has a possibility the worker would inhale the RI such as rooms using RI. Especially for highly
concentrated RI, room gas monitor or iodine monitor is may installed for real-time monitoringof airborne radioactivity
2.1.3.2 Surface Contamination Measurement
Surface Contamination is measured by direct measurement method with smear method or
survey meter. It is required to measure contamination monitoring room which is entrance ofthe restricted area, room using RI and disposal work room.
Measurement points are determined, focusing on points with high chance ofcontaminations such as tables, hoods, floor around sink or on highly used point as entrance ofeach operating room. Hand foot monitor detects floor surface contamination by measuringpersonnel with slippers on, so that contamination status is immediately recognized.
If any contamination was detected, decontamination of the floor is performed, or
preventive measure of spread out of the contamination would be taken immediately. Somefacilities provide measurement results to users to draw attention on a regular basis.
2.1.3.3 Measurement of Leak Dose Equivalent Rate
Leak Dose Equivalent Rate is measured by ionization chamber or scintillation survey meter.
It is required to measure operational, storage and disposal facilities, and at boundary ofcontrolled areas and site.
Area monitor is installed in possible points with maximum dose equivalent rate, large
fluctuation in dose, in locations where personnel stay most of time or boundary of controlled
area. In many cases, the area monitor conducts real-time monitoring of dose rate by62

FNCA Consolidated Report on Radiation Safety (Japan)

communicating with radiation monitoring system.
2.1.4 Radiation Protection of the Public
2.1.4.1 RI Usage Facilities etc.
Dose criteria (levels of radiation or concentration of radioisotopes in air or surface) incontrolled areas as well as the concentration limits for the releases and discharges of effluentsfrom radioisotopes are stipulated and prescribed in the existing rules and regulations. For theprotection of the general public against exposure to radiation, the law requires the use of
appropriate material and thickness for shielding to achieve the desired dose limits for thegeneral public. Other requirement specified in the law is for radioisotopes (RI) facilities toestablish an exclusion boundary area (reasonable distance from public domain) including theresidential area for RI facilities workers, with an effective dose level which is defined not toexceed 250 uSv/3 months.
2.1.4.2 Medical Sector
Guidelines (residual radioactivity and dose rate) and safety instructions related to releaseof patients administered with after therapy with unsealed radionuclides, brachytherapy are
established for the safety of the family, patient comforters and carers , and the general public.
2.1.4.3 Scrap and Metals, etc.
Now that the scrap metals are distributed worldwide by cross border trade, not only
workers engaged in ironworks and in metal production industries but also general public will
be exposed in radiation from recycled products including orphan sources mixed in scrap
metals. Thus, the government’s customs agency installs radiation monitors at the points ofentry and exit of the shipping ports, scrap metal companies install radiation monitors in a yard
entrance so as to ensure that every truck carrying scrap metals are properly monitored fororphan sources and radioactively contaminated scrap metals.

Fig. 10: Image of truck radiation monitor

2.1.5 Radiation Emergency Response
2.1.5.1 Definition of Accident (emergency situation)
A radiation accident is a situation caused by an unexpected event that deviates from anormal operation of facilities and workflow such as out of regulatory control of radiation
source. This accident can be caused by earthquake, fire and other hazards/disasters (flood andpower failure etc), deliberate offense like theft and pilferage, and machine failure.

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Measures in case of accidents and emergencies are defined by the regulations of the
Ministry of Education, Culture, Sports, Science and Technology(MEXT) and the Ministry of
Health, Labour and Welfare(MHLW) and other government agencies. Should these eventsoccur, the employer is required to report promptly to a jurisdiction ministry and a relatedorganization.
2.1.5.2 Examples of Accidents while Using RI at a Nuclear Medicine Facility andTransporting (emergency situation)
The examples here include the following situations:a) There is a possibility of fire and catch fire
(vaporization and evaporation of radioactive materials )b) There is a difficulty to immediately stop irradiation due to damage of shielding
materials for external radiation caused by hazards such as earthquake while
irradiating.
c) Radiation Source has fell off from its containerd) There is inability to store the radiation sources into their container caused bybreakdown of remote devices.
e) A radiation source is missing due to theft/ lossf) The local exhaust ventilation system or the emission source enclosure system does
not function properly due to faults or damage.
g) A great deal of radioactive substance has leaked, spilled or been scattered.
2.1.5.3 Where to report
The place to report varies according to jurisdiction or cases. The example includes
Ministry of Education, Culture, Sports, Science and Technology(MEXT), Jurisdiction labor
standards office, police station, fire department, Ministry of Land, Infrastructure, Transport
and Tourism, Public health department, and National Personnel Authority.
2.1.5.4 Medical Examination etc.
(Ordinance on Prevention of Ionizing Radiation Hazards)
The employer shall immediately have those workers falling under any one of thefollowing categories receive the medical examination or treatment by a medical doctor, andalso report to the head of relevant labor standards office.
・Those who were in the zone when an accident occurs.
・Those who have exposed effective dose or equivalent dose over the limit
・Those who accidentally inhaled or orally took in a radioactive materials.
・Those whose contamination level of their bodies cannot fall below one ten by means ofwashing and so on.
・Those whose wound is contaminated2.1.5.5 A case that you find radioactive materials(response to accidents regarding orphan sources)
Based on the Radiation hazards prevention law, a permission or notification is required if
you wish to use over a certain amount of radiation materials. MEXT requests on their website
and other media to report if unapproved radioisotopes materials or those suspected were64

FNCA Consolidated Report on Radiation Safety (Japan)

found and also warns against touching or moving them without discretion.
The followings are to be checked by MEXT if a radioactive material has been reported.
[Items to be reported]a) Name and contact details of reporterb) Time when it was foundc) Place where it was foundedd) State and label of the matter found etc.
e) Approximate dimension, weight, and quality of the materialf) Dose rate, radiation survey meter or measuring instrument, and measurement
methodg) Situation around the found place (if there is a house or not etc.)
2.1.5.6 Preparation of radiation emergency response manuals
In RI Application facilities, radiation emergency response manuals and check lists areprepared and disseminated among the workers in case that an accident occurs. The following
cases are considered in these manuals and check lists.
a) Fireb) Earthquakec) Ambulance vehicle neededd) Radiation exposure (lose of radiation sources, continuous irradiated state due toequipment failure, inadvertent external exposure, internal exposure, and bodycontamination)e) Expansion of contamination of unsealed sources（gas, dust, and liquid）
f) Loss or theftg) RI outside their control foundh) Accident during transportationi) Communication system and contact information（in and out of the facilities）
2.2 Radiation safety management in Research Reactors
2.2.1 Radiation Safety Management System
The safety management system in research reactors is regulated in the Act on theRegulation of Nuclear Source Material, Nuclear Fuel Material and Reactors of Japan as wellas Nuclear Power Plants. The radiation safety procedures are ruled in the inside-rule ofevery facility, but much simple relative to those of NPPs.
The radiation safety management at the reactor facility consists of the management ofradiation workers, radiation control of working area, control of contamination level on
carry-out goods and control of radioactive discharge (gas and liquid) to the environment.
2.2.2 Radiation Protection for Radiation Worker
The reactor room is designated as controlled area and is equipped with some radiation
protection apparatuses and instruments, such as radiation monitors (Gamma and Neutron),survey meters (Gamma, Neutron, Beta etc.) and radioactive air concentration monitors. The
air pressure of reactor room is kept in lower level than outside so that radioactive materials
cannot flow out to the general area. For most research reactors, the criticality monitoring is
not necessary except some of the special types of critical assembly facilities. Access control

65

FNCA Consolidated Report on Radiation Safety (Japan)of workers is a little bit strict and all the workers who are going into the reactor room areregistered during their stay in the room. When they exit from the reactor room, radioactive
contamination of the body or carry-out goods and exposures of workers are checked and theexposure value would be reported if it is over the recording level.
All the radiation workers have to wear an experimental or working suit and safety shoes toavoid contamination of their own bodies and clothes. The radiation workers also must wear
either one or two types of personal dosimeters to measure and record their exposure values.
Direct reading personal dosimeters are useful for their exposure control by themselves. The
radiation and air contamination (dust or gas) monitoring apparatuses are often used to observe
the status of the working area. If the air contamination level is exceeded a designatedcriterion, appropriate radiation protection measures, such as wearing air mask, etc. areconducted. When work finished, survey checks on surface contamination are made withsurvey meters for workers, tools and floors.
2.2.3 Radiological Protection for Radiation Area
Radiation and air contamination levels at the working area are continuously watched by
the radiation protection officers using monitors and recorded with the electric devices. And,
when something unusual happened, the radiation protection officers would notify the situation
to the workers and take any protection measures, if necessary. Figure 11 shows an exampleof the air contamination monitoring at controlled area.

Fig. 11: An Example of Air Contamination Monitoring at Controlled Area

The control of discharge of radioactive materials to general environment is also quite
important for research reactors. The total amount of radioactive discharge is limited in theinside-rule of each facility, but the actual amount of discharge is quite smaller than the limited
value. For some research reactors, main radio-nuclides in the air waste are Ar-41 andTritium (H-3) produced in the surrounded air or water. The fission products, such as I-, Xe-,etc., are discharged in the air quite a little from general water-cooling type research reactors.
Figure 12 shows an example of the air monitoring system of research reactor facility. The
radioactivity level in the air is watched all the time with dust or gas monitors. Dust andvolatile materials are also sampled with air filters and the filters are measured with suitableradioactivity measurement devices such as, Ge detectors and/or gas flow counters, for detailed
investigation of radioactive air concentration level.

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FNCA Consolidated Report on Radiation Safety (Japan)

The liquid waste from the controlled area is once stored in a disposal tank at each facility
and then checked its radioactive concentration level by sampling. If the value of radioactive
concentration in the liquid waste is less than a designated level, the liquid waste is discharged
into the sea. If the value is exceeded the level, the waste is transferred to the disposal
treatment facility and stored.

Fig. 12: An example of monitoring system for airborne radioactive waste at research reactor facility

2.2.4 Radiological Protection for the Public
The exposure of public people is evaluated by the calculation using the amounts ofdischarged air and liquid radioactive materials. And all the amounts of discharged radioactive
materials and evaluated dose values of the public are reported to the Government and the
local governments. In addition, most of the organizations that operate research reactors set up
the environmental measurement apparatuses, such as monitoring stations or monitoring posts,
inside and outside of the site, and they are keeping observation on radiation level and others
all the time.
2.2.5 Radiation Emergency Preparedness
In emergency situations, such as fire, earthquake or any troubles inside the facility, all themembers of the facility will gather immediately at any time and engage in the recovery work.
The training on emergency preparedness is also conducted once or twice a year to keep
workers’ motivation in good condition.
2. 3 Radiation Management in Nuclear Power Plants
2.3.1 Radiation Safety Management System
Nuclear power plants construct radiation safety management system with the director at

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FNCA Consolidated Report on Radiation Safety (Japan)

the top. Fig.13 shows an example of the system.
Director
Reactorinstallation
personnel

Radiation
management
department

Working
department

Contact/Consultation/Direction/Advice
Contact/Consultation
Direction/Counsel

Contact/Consultation
Direction/Advice
Contact/Consultation
Direction/Counsel

General manager

Opinion offer

Direction/Counsel
Contact/Consultation

Radiation
control chief

Radiation
protection
direction

Operation
manager

AdviceHazardprevention
manager

Radiation
control staff

AdviceDirection
Measurement

WorkerAdviceHazardprevention staff

Contractor

Education
Personal exposure management

Fig.13: Radiation Safety Management System

2.3.2 Radiological Protection for Radiation Worker
In nuclear power plants, the amounts of doses for radiation workers are managed to keep
the legal dose limits, 100 mSv for 5 years and 50 mSv for one year, as well as the planned
doses which are directed every work. In this way, we try to aim at the doses as low asreasonably achievable (ALARA).
People who work in radiation-controlled areas are supposed to register as “Radiation
Workers”. At the time of registration, they are required the past doses, the results of medical
examinations by doctors, the records of education such as knowledge about radiation andrules for radiation works and so on. Only after the above confirmation, they can work inradiation-controlled areas.
After the registration, they undergo periodical medical examinations, external dose checks
by electronic type pocket dosimeter or glass badge and internal dose checks by whole bodycounters. Then the total amounts of personal exposure doses are notified to them
respectively.
The Radiation Dose Registration Center for Workers (RADREC) collects personal doserecords for radiation workers periodically. Therefore their dose records are centralized andmanaged uniformly, even if they work in other places. This system is called “Radiation
Dose Registration and Management System” (Fig.14). For each person, Radiation Dose
Record Booklet (Radiation Passport) is issued by agencies authorized by the RADREC. The
booklet contains necessary information about radiation protection management such as
bearer’s identification, historical exposure results, educational records and so on.

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Registration/Referral

Radiation Dose Registration
Center for Workers
ReportReportBooklet issuing
institution

Station A

Station B
NoticeWork

Work

NoticeBooklet issue
Bringing

Bringing

Fig.14: Radiation Dose Registration and Management System

Radiation management ground plan

Working area
Planned dose（daily，whole，personal max etc.）
Dose reduction measures
Radiation protective equipment
Work environment monitoring plan
Estimation of waste generation

Radiation work plan/admission
Protection instructions

Daily radiation protective equipment
Daily planned dose
Daily dose reduction measures
Alarm setting value of dosimeter

Work environment monitoring
Work

Confirmation difference between plan and result

Radiation work report

Fig.15: Radiation Work Flow (From plan to report)

Fig.15 shows the radiation work flow. By each step, PDCA (Plan-Do-Check-Action) has
been repeated conventionally to reduce exposure dose.
2.3.3 Radiation Area Management
We prevent unnecessary exposures by setting radiation-controlled areas where a total
effective dose from external radiation or radioactive materials in air and surface density ofradioactive materials is exceed or suspected to exceed the legal limits. For figuring out thedose rates in the radiation-controlled areas, we settle radiation monitors. And then,continuous measurements and monitoring are conducted. To understand the contamination
conditions, we also measure and watch the concentration of radioactive materials on thesurface of the structural objects or in the air. According to the dose rates and contaminationlevels, we divide the radiation-controlled areas into some categories by using walls and fenceswith signs.(Fig.16)
In order not to bring out radioactive materials from radiation controlled areas, we aresupposed to change into special clothes and shoes etc. in the radiation-controlled areas which

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FNCA Consolidated Report on Radiation Safety (Japan)

have probability of contamination. And we are also supposed to take contamination tests forgoods and body surface to make sure of no contamination when we exit from theradiation-controlled areas.

Hand-wash station

Exit monitor
Monitor for carrying goods

Controlled areas

Access control device
Work information input device
APD* loaning device
Check point*Alarm Pocket DosimeterFig.16: Divisions of Areas inside the Radiation-controlled Areas

2.3.4 Radiological Protection for the Public
2.3.4.1 Regulation and Guideline(a) During normal operation
Annual dose limit (1mSv/y) for the public is prescribed by the regulation as shown in
Table 1 to ensure the protection of the public against radiation from nuclear power stations inJapan. This is based on ICRP recommendation in 1990.
To allow compliance with the regulation with wide margins, a dose target (50μSv/y) forthe public is prescribed by guideline. This is a target value for the public dose due to theradioactive materials released from nuclear power stations. And this is a criterion to judge that
releases reduction systems are arranged so as to keep doses to the public as low as reasonably
achievable (ALARA).
A dose target (50μGy/y) for the public due to radiation from the nuclear power station isprovided in a Nuclear Energy Special Committee report.
(b) Under accident condition
To protect the public from significant radiation effects, dose criteria for postulated
nuclear power station accidents are also stipulated in the guidelines in view of reactorsite suitability and design adequacy.

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As criteria for reactor site suitability, the target values of individual dose andpopulation dose for severe accidents and hypothetical accidents are established as shownin Table 9. The severe accident is defined as an accident that is less likely to occur. The
hypothetical accident is defined as an accident that is unlikely to occur from a technicalviewpoint.
On the other hand, as criteria for design adequacy, the target value of dose isestablished for the design basis accident.
Table 9: The dose limits for the public in the Japanese regulation and guidelines.
Type

Dose criterion

Regulation (limit)

Annual dose

1 mSv/yGuideline(targetvalues)Annual dose for release of radioactive
materials

50 μSv/yAnnual dose for radiation from facilities

50 μGy/yDuringnormaloperation
Underaccident
condition

Designaccident

basis Effective dose

Severe accident
Hypotheticalaccident

5 mSv

Whole-body dose

0.25 Sv

Thyroid dose (child)

1.5 Sv

Whole-body dose

0.25 Sv

Thyroid dose (adult)

3 Sv

Population dose

20000 man･Sv

2.3.4.2 Nuclear power plant design(a) Policy of radiation safety design
Releases reduction systems, radiation protection equipments, and radiation monitoringand sampling systems are provided at nuclear power stations to establish radiation safety
for public and radiation workers. The releases reduction systems and the radiation
protection equipments are designed based on the ALARA concept, with specifications for
reducing release or exposure dose to a level as low as reasonably achievable. Judging
ALARA approach is accomplished by compliance with the dose target based on theguidelines.
In case of an abnormal event, the systems and the equipments are designed to achieve“shutdown of the reactor,” “cooling of the reactor,” and “confinement of radioactive
materials”. They are also laid out to attain habitability in the control room and thetechnical support center to allow operational actions. Furthermore, the releases reduction
systems and the radiation shielding facilities are provided to ensure compliance with thedose targets by the guidelines during the abnormal condition.
(b) Radiation protection design(i) Releases reduction systems
Releases reduction systems are designed so as to store radioactive gaseous waste
emitted as a result of the degassing process of the reactor coolant, to monitor the71

FNCA Consolidated Report on Radiation Safety (Japan)

concentration of radioactive materials and to release the waste gas after its radioactivity is
sufficiently reduced.
The ventilation systems are intended to remove radioactive materials from the exhaust
generated in radiation controlled areas by using iodine filters or high-performance
particle filters. The systems also monitor concentrations before releasing waste gas.
Reactor coolant, equipment drains, floor drains and effluents from hand-washing,laundry, and hot shower systems are to be filtered, demineralized and concentrated by theevaporator. This is to ensure that the concentration of radioactive materials in the liquid
waste is sufficiently reduced. Afterward the liquid waste is diluted and released after
checking the concentration of radioactive materials. Concentrated liquid waste
generated from the evaporator is to be solidified. The miscellaneous solid waste and thespent exhaust filters are to be compressed for volume reduction. The low level spentresin, the low level concentrated liquid waste, and combustible miscellaneous solid waste
are incinerated for volume reduction. These solid wastes are put in drums separately for
temporary storage. Storage capacity for the high level spent resin is secured to store theresin generated throughout the plant life.
Releases mitigation systems corresponding to postulated events are provided so as tokeep doses below the target levels for site suitability and design adequacy. Moreover,
event mitigation manuals have been developed with the aim of reducing the amounts ofreleases under severe accidents.
(ii) Shielding facilities
In Japan, since it is difficult to secure a sufficiently large site for a nuclear power
station, it is critical to reduce radiological effects on the public to as low as reasonably
achievable by thoroughly shielding radiation from facilities. In reactor facilities, theshielding designs of the containment vessel, turbine system (BWR), and waste disposal
and storage facilities are important. For reactor auxiliary buildings, reasonable shielding
designs are implemented by optimizing equipment layouts.
Currently, large components are being replaced for facility maintenance after about 20
years of operation.
Accordingly, additional waste storage facilities to store large-size radioactive waste
arising from the replacement are being built with a satisfactory shielding design thateliminates the harmful effects of radiation on the public.
(iii) Radiation monitoring systems
In operating reactor facilities, monitoring systems are designed to ensure that theamounts of releases are below the prescribed releases targets for gaseous and liquid waste.
At the same time, these systems are intended to perform sampling and measurement
before releasing waste. Depending on the monitored level, the effluents can be returned to
the radioactive material processing systems as necessary.
Furthermore, dose rates in the vicinity of the plant and the concentration of radioactive
materials in environment (samples) are measured so as to monitor the impact on theenvironment.
To detect any anomaly at a nuclear power station as soon as possible, and to prevent
any abnormal release of radioactive materials, radiation monitors for leakage detection72

FNCA Consolidated Report on Radiation Safety (Japan)

are installed in the systems of reactor coolant, main steam, waste treatment, andventilation.
Grass (sample)
Soil (sample)
Water (sample)

Site boundaryLand
Monitoring post
Sea

Nuclear power station

Fish (sample)

Fig. 17: Environmental monitoring and sampling during normal operation

2.3.5 Radiological Emergency Response
2.3.5.1 Legislation and guidelines
Following the critical accident at the reprocessing facility in Tokai-mura (Japan) in
September 1999, the Special Law of Emergency Preparedness for Nuclear Disaster wasenacted in December of the same year, whereby a disaster prevention scheme at the time of
emergency at a nuclear installation was established.
The law clearly defines the duties of the nuclear operator in case of emergency, obligation
to notify an abnormal event, declaration of a nuclear emergency, mechanisms for setting up
Nuclear Emergency Response Headquarters and Local Nuclear Emergency Response
Headquarters, and the roles of an Off-site Center.
An abnormal event should be notified when the dose rate near the site boundary reaches 5
μSv/h or if the event may develop into a nuclear emergency involving the activation of theemergency core cooling system (ECCS). A nuclear emergency is declared when the dose
rate near the boundary of the plant site reaches 500 μSv/h or if the event has evolved into theloss of all reactor shutdown functions.
In the wake of the Three Mile Island reactor accident in 1979, emergency preparedness
guidelines were established in 1980 under the Basic Law for Emergency Preparedness, andthey were revised in May 2000. They clearly define technical elements in nuclear
emergency activities as well as tasks to be fulfilled in the aspects of emergency monitoring,
emergency preparedness, emergency exposure medical treatment, and so on.
2.3.5.2 Nuclear disaster emergency countermeasures
Upon notification of an abnormal event at a nuclear power station from the operator
according to the Special Law, an Off-site Center will be set up.
As the event progresses, the central government declares a nuclear emergency, which
prompts organization of Nuclear Emergency Response Headquarters within the government,
Local Nuclear Emergency Response Headquarters at the Off-site Center, and a Joint Council

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FNCA Consolidated Report on Radiation Safety (Japan)

for Nuclear Emergency Response.
The central government, local government, police, fire defense authorities, self-defense
forces, operator, and experts will be summoned to take part in disaster response
countermeasures in multiple functional groups under the leadership of Joint Council for
Nuclear Emergency Response.
The central government is now implementing the technical assistance necessary fordeveloping a system in which the government participates in the prediction andcountermeasures management of the accident progression. This includes ascertaining theabnormal state of the reactor facility based on online information from the nuclear power
station, operates a system that predicts the evolution of the event, predicts radiation exposure
effects resulting from released radioactive materials in the vicinity of the site using local
meteorological information on the basis of the SPEEDI system, and issues evacuation
advisories to the local residents in an appropriate manner if necessary. Additionally, toestablish a thorough preparedness structure in case of nuclear disaster, nuclear emergency
response drills are regularly conducted jointly by the central government, local governments,
operators, and other parties concerned to make sure that the communication system,
command system, decision-making process, evacuation process, and roles and functions ofindividual participants work effectively.
National Government

Prefectural
Emergency Response Operations Headquarters

Nuclear Emergency Response Headquarters

Offsite Center
National Government
Local Headquarters

Prefectural
Local Headquarters

Joint Council for Nuclear
Emergency Response

AdviceMunicipal

Nuclear Licensee

Participation
Nuclear Safety
Commission

Local Headquarters

Instruction for
Shelter/Evacuation

Municipal
Emergency Response Operations Headquarters

Expert (Technical support)

Residents･Police･Fire Department･Self-Defense Force

Fig. 18: Emergency Preparedness Organization

2.3.5.3 Response to a radiation accident
Possible radiation accidents at nuclear power stations include excessive exposure andradioactive contamination at times of patrol inspection during operation, radioactive
equipment inspection as part of periodical inspection, and handling of spent resin, spent filters,
and other radioactive waste.

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To prevent these radiation accidents, radiation measurement and contamination inspection
are performed in advance, as necessary; work plans are prepared and planned doses are preset
for radiation work; and activities are performed under radiation control.
Importantly, education and training sessions and mockup tests are conducted in pursuit ofhigh safety awareness and reduced exposure time.
In case a radiation accident occurs, the top priority is placed upon the safety of humans
and lifesaving. If there is critical contamination or exposure, treatment by physicians is
mandatory. In the meantime, the plant manager and workers around the accident site should
be notified of the occurrence of the accident, and measures necessary for preventing
expansion of the accident or spread of contamination must be put in place.
2.4 Radiation Safety Control at the Radioactive Waste Treatment Facility(Regarding Radiation Safety Control of the Low-Level Radioactive Waste Disposal Facility)
2.4.1 Radiation Safety Management System, Radiological Protection for
Radiation Worker, and Radiological Protection for Radiation Area
Radiation safety control applied at Japan Nuclear Fuel Ltd. (JNFL) 's Low -Level
Radioactive Waste Disposal Center which is located at Rokkasho-Mura, Aomori Prefecture, isdifferent from the one applied to nuclear power plants , and has a special feature that its
method is changed gradually in accordance with the attenuation of radioactivity of radioactive
waste. This is described as the "Phased Management".
 Regarding Waste Packages
At present, there are two facilities at the Low-Level Radioactive Waste Disposal Facility at
Rokkasho, namely, No. 1 Disposal Facility and No. 2 Disposal Facility, where two different
types of waste packages are buried. In No.1 Facility, such liquid waste as water used inrinsing the floor of nuclear power plants is evaporated, concentrated and solidified, which isthen put into drums after being homogenously solidified by cement, asphalt or plastic. Waste
packages disposed in No. 2 Disposal Facility consist of metal（pipes and plates etc） andconcrete scraps produced as result of periodic inspection works. These are cut, compacted
or dissolved as necessary, and are placed in drums and solidified with mortar.
Among waste packages to be disposed, there is incongruity in radiation levels in each waste
package, but the level is below the upper limit of concentration defined by law, which fact isconfirmed before transportation from nuclear power plants, and on each waste package, signs
indicating it as radioactive waste and identification number are shown. Upon arrival at
Rokkasho Disposal Facility, Government confirmation that each package conforms totechnical standard required by law regarding its outward appearance and identification
number is given before being disposed.
The principal technical standard for waste package consists of the following:
1. That the waste is solidified inside the package
2. That the waste does not exceed the maximum radioactive concentration
3. That there is sufficient strength
4. That signs and identification numbers are place.
 Regarding the disposal facility
Waste packages are placed inside the disposal facility (pit) made of reinforced concrete.

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When fixing waste packages inside a pit, attention should be paid so as to balance theconcentration and types as facility as a whole, by not placing waste packages extremely close
to the type other than that which is solidified by cement.
Waste packages, when confirmed upon reception, do not need to be verified package
by package after their disposal, since radioactive waste in principle attenuates according
to its half-life, and since, for dose evaluation of the general public, control is done as adisposal ground as a whole.
After waste packages are fixed fully inside a pit, spaces between the drums are filled inwith mortar, and further, a cover made of reinforced concrete is placed over the entire disposal
facility, shielding radioactive waste completely. The entire facilities is covered withwater-impervious Bentonite clay．This is then covered with original soil、which is planted withgrass, and this will remain a controlled site for approximately 300 years.
 Regarding Phased Management
Next, "Phased Management" means that the waste disposal facility is managed bychanging method into three phases as follows:
At the First Phase, where the radiation level at the start of burial is not sufficiently low, bymeans of artificial barriers such as concrete pits and drums, waste packages are shielded sothat they do not leak radiation and radioactive material.
At the Second Phase, upon completion of the First Phase, radioactivity becomes low after
the passage of certain time period, stabilizing measures of the surrounding soil is effected,
since it becomes possible to restrain the transfer of radioactive material sufficiently by meansof the surrounding soil even if the disposal facility is deteriorated.
At the Third Phase, upon completion of the Second Phase, when radioactivity declines
sufficiently after the passage of certain period, the situation becomes safe enough only byinterdicting digging. After 300 years, the radiation level of the waste packages becomesvery low, which means safe enough so that no regulation shall be applicable for the waste
packages as radioactive material.
Fig. 19: Attenuation by aging of total radioactivity

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Table 10: Way of Thinking of Phased Management

Scheduled
PeriodPurposeControlManagement

1st PhaseTime elapsed after
initial disposal
No.1:30-35 years
No.2:25-30 years
Containment withindisposal facilities

2nd Phase

3rd PhaseTime elapsed after
1st Phase:30 years

Time elapsed after
1st Phase:300 years

Prevention ofPrevention of transfer
transfer using
primarily throughdisposal facilities
cover soil
and cover soil
・Establishment of disposal maintenance area, monitoring of waste
burial, restoration of cover soil
・Environmental monitoring・Establishment of supervised area
・ Monitoring of density of radioactive ・Restrictions on
excavation, etc.
substances in groundwater・Drainage of water, supervisory facilities
water drainage
・Monitoring for any ・Monitoring ofleakageleakage conditions
・Repairs of disposal
facilities, etc.

 Regarding Measures for reducing occupational exposure
Both Measures relative to facility and measures relative to management are undertaken.
Following measures relative to facility are undertaken:
・ Shielding, in accordance with the area of access by workers.
Design criteria for shielding are as follows:
Table11: Design Criteria for Shielding

Areas
Outside of Radiation Controlled Area
Inside Radiation ・48 hours entry /week
Controlled Area
・24 hours entry/week
・10 hours entry/week
・1 hour entry/week
・Entry normally unrequired

Dose
Rate
Equivalent(μSv/h)
≦
6
≦
10
≦
20
≦
50
≦ 500
＞ 500

The actual thickness of the shielding wall is 20cm～90 cm for the Control Building.
For the Disposal Facility, shielding is by concrete of approximately 50 cm.
Further, after fixing the drums in pits, by placing a temporary cover of 50 cm thickness,
exposure from the pit opening is reduced.

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FNCA Consolidated Report on Radiation Safety (Japan)

・Crane for the handling of waste packages and inspection equipment of waste packages areautomated and remote controlled.
・Entry-exit Control Units and Radiation Measurement Equipment are installed for the
management of occupational exposure .
Table12: Measures for Radiation Protection Equipment

Items
Shielding

Remote Controlled
Automated
Radiation Control Facility

Example of measures
Thickness of concrete of the Facility
・Control Building（Principal Parts）
Approx. 20～90cm
・Disposal Facility
Approx. 50cm
Various cranes
Inspection Units for Waste Package
Access Control Facility
Radiation Measurement Units, etc.

As measures from the management point, following are undertaken:
・ Unitary management of Company employees and subcontractors' personnel byprofessionalization of Radiation Management Sector.
・Limiting access by establishing "Radiation Controlled Area"
・Access control of workers entering "Radiation Controlled Area".
・Personal dose control of workers.
・Radiation protection education to workers.
・Radiation work management such as monitering of dose rate in work area.
These measures are basically similar to those implemented at nuclear power plants.
 Regarding the evaluation of environmental impact(Radiation protection of the general public)
Considering the impact on the environment by leakage of radioactive material from the
Disposal Facility, it is important that there should not be harmful impact on humanenvironment through groundwater.
The place where the Disposal Facility is located in Rokkasho, an impermeable bedrock
called the "Takahoko Layer" is distributed along fairly shallow spot of several meters from theland surface, so that the groundwater is flowing mainly near the surface only. Further, since
the landscape is a plateau surrounded by rivers and marshes, the groundwater consists mainlyof rainwater which has seeped slowly into underground, so that we can say that this is an area
where the groundwater is not abundant.
Since waste packages are placed in pits made of concrete, where the paces inside the pit arefilled by mortar, and pits are surrounded by soil mixed with bentonite, it should be noted thatsufficient measures are taken against the groundwater. Also, even in unlikely cases of thegroundwater seeping into the Disposal Site, since water seeping through the surrounding
porous concrete can be drained without reaching the waste packages until the Second Phase, it
is unthinkable that the radioactive material can easily leak out of the Disposal Facility.

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FNCA Consolidated Report on Radiation Safety (Japan)

Table 13: Ground Water at the location of the Disposal Facility/Safety of locating below Ground Water

Ground Water at the location of Disposal Facility① Distributed in comparatively shallow spots of the impermeable
Takahoko Layer.
② Groundwater originates mainly from the rain water which seepedslowly to underground

Safetyof locating below
Groundwater
is not groundwater
plentiful① Radioactive waste is solidified into drums by cement, etc.
② Disposal Facility is made of reinforced concrete.
③ Mortar is filled in.
④ Disposal Facility is covered by the Takahoko Layer and the soil mixed withbentonite, which do not pass water easily.

⑤Water which seeps into the Disposal Facility can be drained（Up to
the Second Phase)Radioactive Material does not easily leak.

Table14： Comparison of Water Permeability Factor

Water permeability Factor（cm/S）
Approx. 10－４
Approx 10－５
Approx 10－７
Approx 10－１０

Division
Quarternary
The Takahoko Layer
Bentonite Mixed Soil
Concrete

However, assuming the worst case of radioactive material leaking prematurely,
evaluation of impact on in-taking maritime products from the marsh which is the ultimate
reaching point of ground water is being undertaken.
Condition of evaluation is maximum 0.075 micro Sv per year, upon estimating thepremature deterioration of the Disposal Facility, the routes through which marsh products areeaten, namely: from the groundwater to the stream to the marsh, from the marsh water tomarsh products. This is well below the yearly dose criteria of 0.10 micro Sv which is a

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FNCA Consolidated Report on Radiation Safety (Japan)

provisional target.
Dose equivalent evaluation is undertaken on assumption that the marsh water near the
Disposal Facility may be used for drinking by the general public or for the cattle, after the
expiration of the management period (300 years). This evaluation result shows that eventaking into account, the cases of intake through various route, the dose equivalent is 0.13
micro Sv/year, which is so small that no impact is at all likely.
Table 15: Dose Equivalent Evaluation for eating maritime products
Premature deterioration of Disposal Facility
Carried by groundwater to marshes

Condition for evaluation

Marsh water to marsh product
Eating marsh products daily & continuously

Max.

Result of evaluation

7.5×10－３ ｍSv/ｙSent to the sea from Obuchi Marsh

Impact on maritime
products

Big volume of diluted water
Impact can be fully ignored

Table 16：Evaluation Result After Expiration of the Management Period(General)

Unit(mSv/y)
Evaluation Route of Dose
Dose Equivalent
Equivalent(i) Internal Exposure due to eating
Approx.7.5×10－５
marsh product(ii) Internal Exposure due toApprox.1.3×10－４
drinking marsh water(iii) Internal Exposure due to Farm products
eating dairy products produced by Approx. 9.1×10－５
using marsh water
Dairy Products
Approx. 2.9×10－５(iv) External & Internal Exposuredue to farm work using marsh
Approx. 5.5×10－５
water for production(v) External & Internal Exposure
Approx. 8.3×10－５
for construction works of housing(vi) External & Internal Exposure
Approx. 0.0015
due to residence in the area

80

Judgment Dose
0.01 ｍ Sv/y defined in"the Basic Way ofThinking"
asaprovisional target（For reference）
Natural radiation
Approx.1mSv/Year

FNCA Consolidated Report on Radiation Safety (Japan)

Fig. 20: Evaluation Result after Expiration of the Management Period

2.4.2 Radioactive Waste Management in the Research Facilities
In the research facilities, radioactive waste is generated from research reactors, hotlaboratories, nuclear fuel laboratories, radioisotope laboratories, accelerators, facilities
modification and decommissioning, etc. This kind of waste includes various sorts of materials
and radio activities.

Operation & MaintenanceAccelerator Operation

Post Irradiation Examination

Radiochemical Experiment

Application Research

Modification & Decommissioning

Gaseous waste is treated at the generating facilities by filtration, dilution, decay, etc. After
that, it's discharged under the radiation monitoring into the atmosphere.
Liquid waste which radioactivity concentration is less than discharge standard isdischarged into environment. Other liquid waste is treated at the liquid waste treatment
facilities. Then concentrate and sludge are solidified into a container (drum), and treatedliquid is discharged into environment.
Radioactivity
measurement

Treated liquid
Concentrate
SludgeEvaporation

Sedimentation

Filtration

81

Solidification

Discharge

FNCA Consolidated Report on Radiation Safety (Japan)

All of solid waste is transported to
the
waste
treatment
facilities.
Incombustible waste is compressed,
combustible waste is incinerated, andlarge size waste is cut and sorted. Thenthese are packed into containers. Highradiation dose waste is handled in theshield cell and packed into a shieldcontainer.

Incombustible

Combustible

Large size

Compression

Incineration

Dismantling

The waste packed into the container isstored in the storage building. These waste
packages are checked on a periodic basis andmaintained in safe condition.

Storage & Radiation Control

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6. Kazakhstan
Part 1. Radiation Safety in RI Facilities ... エラー! ブックマークが定義されていません。
1.1. General.................................................. エラー! ブックマークが定義されていません。
1.1.1 Legislative Framework and Policy for Radiation Safetyエラー! ブックマークが定義されていません。
1.2 Outline of Radiation Facilities and Radiation sourcesエラー! ブックマークが定義されていません。
1.2.1 Number of specialists and workers in related organizationsエラー! ブックマークが定義されていません。
1.2.2 Number of radiation facilities including related facilitiesエラー! ブックマークが定義されていません。
1.2.3 Activity and number of radiation sources and generatorsエラー! ブックマークが定義されていません。
1.2.3.1 Future plans and issues to be solved... エラー! ブックマークが定義されていません。
1.3 Education and Training ........................... エラー! ブックマークが定義されていません。
1.4 Standardization on radiation and radioactivityエラー! ブックマークが定義されていません。
Part 2 Status of Radiation Safety Managementエラー! ブックマークが定義されていません。
2.1 Radiation safety management in various RI usageエラー! ブックマークが定義されていません。
2.1.1 Radiation Safety Management System . エラー! ブックマークが定義されていません。
2.1.2 Radiological Protection for Radiation Workerエラー! ブックマークが定義されていません。
2.1.3 Radiological Protection for Radiation Areaエラー! ブックマークが定義されていません。
2.1.4 Radiological Protection for the Public... エラー! ブックマークが定義されていません。
2.1.5 Radiation Emergency Preparedness ...... エラー! ブックマークが定義されていません。

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)

6. Kazakhstan
Part 1. Radiation Safety in RI Facilities
1.1. General
The Committee of Atomic Energy of the Ministry of Industry and New Technologies of the
Republic of Kazakhstan is the legal successor of the Atomic Energy Agency of the Republic of
Kazakhstan established in 1992.
In accordance with its Status the Committee executes control and supervision in the field ofsafety and security in peaceful use of atomic energy. Hence the main tasks of the Committee areregulation of the safety issues, supervision over the nuclear and radiation safety and nuclear
security and also over provision of the regime of nuclear weapons nonproliferation when
executing any activity related to the use of atomic energy.
The State licensing performed by the Committee is one of the ways to provide safety of thenuclear activities in Kazakhstan. Licensing is performed with the aim to ensure execution of thelegislation requirements, safety standards and rules in the field of atomic energy peaceful use. The
approved Rules of licensing are one of Committee’s anti-corruption activities describing the orderand terms of licensing procedures including the work with received license applications, theirpreliminary and final processing, conclusion on application and license issue in case of positive
conclusion on application. Any attempt of illegal charging, assistance in registration ofCommittee`s license or other illegal activities undertaken by either its staff and outsideorganizations or individuals shall be immediately reported to Committee’s administration.
The matters of Committee`s work are related to its primary functions implementation:- the nuclear and radiation safety;- nuclear security including physical protection of nuclear and other radioactive materials,
nuclear facilities, transport, combating illicit trafficking of the nuclear and otherradioactive materials, preventing potential acts of nuclear terrorism (within thecompetence of the Committee);- emergency readiness and emergency response measures including international andinterstate cooperation in case of any transboundary nuclear or radiological incidents;- staff training and staff certification in organizations engaged in nuclear or potentially
dangerous radioactive activities;- researches sponsoring to prove the nuclear activities safety;- international cooperation within the Committee`s competence sphere.
The Committee is responsible for maintenance of state systems for accountancy of nuclear
materials and radiation sources. All Committee`s Licensees shall regularly provide data regarding
to the presence and circulation of relevant materials and sources which are in their balance. The
national chart of radiation sources is compiled on the basis of provided data after theverification. The data on nuclear materials quantity are used to maintain the chart and nuclear
materials circulation record in the zones of material balance of the Republic of Kazakhstan. The
reports concerning the nuclear materials presence and circulation are regularly submitted to theInternational Atomic Energy Agency (IAEA) to implement the Agreement between the Republic

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)of Kazakhstan and IAEA with regard to safeguards application in connection with Nuclear
Weapons Nonproliferation Agreement which came into force on August, 1995. The Additional
Protocol to the above Agreement came into force in 2007 and the Committee is also in charge of
its implementation.
RK is a member of Nuclear Suppliers Group (NSG). The legislation, standards and rules ofrepublican nuclear export control correspond to all NSG recommendations. All nuclear export andimport applications shall be agreed by the Committee – the license is issued by the Ministry ofIndustry and Trade. It shall be noted that sale of nuclear or other radioactive materials andradiation sources is to be licensed.
1.1.1 Legislative Framework and Policy for Radiation Safety
The main aim of Committee’s activity is sustainable and cost-effective safety provision in atomic
energy peaceful use, protection of population and humans` habitat from possible negative impact of
atomic energy use.
Factors determining the radiation conditions on the territory of the Republic of Kazakhstan:- Activities of uranium mining and processing enterprises and associated geological works;- Activities of mining and processing enterprises producing the raw material with a highcontent of radioactive elements;- Activities of uranium industry enterprises;- Power and research nuclear reactors, radioisotope products use;
- Nuclear tests carried out in the past.
Nuclear energy use is widespread in Kazakhstan – not only nuclear fuel cycle enterprises but also
wide number of medicine, scientific and other establishments use the radioactive sources. Therefore
Committee controls not only scientific and industrial nuclear complex enterprises but all establishments
engaged in hazardous nuclear and radiation activities in the field of atomic energy use. Isotope products
are used in various fields of economy mainly as so-called ampoule sources of radiation.
One of the most important conditions for atomic energy safe use is legal regulation, responsibilities
allocation between organizations engaged in atomic energy use and state bodies monitoring the nuclear
and radiation safety.
By the Decree of Government of the Republic of Kazakhstan No. 1894 dated back December 29,
1995 the list of state bodies entitled to grant the license for activities subject to licensing was approved.
The Committee of Atomic Energetic of Ministry of Energetic and Mineral Resources included to thatlist.
The Committee executes functions in the set order defined by Decree about the Committee
endorsed by the Order of Executive Secretary of Ministry of Energetic and Mineral Resources of the
Republic of Kazakhstan dated to January 21, 2008 No. 20-K.
The Committee is entitled to grant license for activities related to atomic energy use and to supervise
over the licensing requirements execution within its jurisdiction.
The primary activities in the field of atomic energy use defined by Article 13 of Law “Aboutlicensing” No. 214 dated to January 11, 2007., and Article 5 of Law “About atomic energy use” No. 93
dated to April 14, 1997 and Resolution of Government of the Republic of Kazakhstan No. 270 dated toMarch 19, 2008.
The Law "About the Atomic Energy Use” (No.93 dated to April 14, 1997) establishes legal
standards and principles for regulation of public relations in the field of atomic energy use and aimed to85

FNCA Consolidated Report on Radiation Safety (Kazakhstan)protect humans` health and life, environment and to provide nuclear weapons nonproliferation andnuclear and radiation safety in atomic energy use.
The Law establishes the basic rights of authorized state bodies and officials in the field of atomic
energy use, establishes the necessary licensing of all types of atomic energy use activities.
The Law "About Radiation Safety" (No. 219 dated to April 23, 1998) regulates public relations in
the field of radiation safety to protect the health of population from negative impact of radiation , sets themain principles of radiation safety.
The Law establishes the jurisdiction of the state bodies on provision of radiation safety, general
requirements for radiation safety assessment and radiation safety when using the radiation sources.
The Law "About Licensing" (No.214 dated to January 11, 2007) regulates the state licensing
procedures for any activity or defined activities subject to licensing, sets the basic licensing principles,
types and forms of licenses, sets the list of documents necessary to get the license.
The Law "About Radiation Safety" (No. 219 dated to April 23, 1998) regulates public relations in
the field of radiation safety to protect the health of population from negative impact of radiation , sets themain principles of radiation safety.
The Law establishes the jurisdiction of the state bodies on provision of radiation safety, general
requirements for radiation safety assessment and radiation safety when using the radiation sources.
The Resolution of the Government of the Republic of Kazakhstan (No. 270 dated to March 19,2008) "On Approval of Rules of Licensing and Qualification Requirements to Activities Subject toLicensing in the Field of the Atomic Energy Use” establishes the list of activities subject to licensing in
the Committee of Atomic Energetic (in compliance with the Law “About Atomic Energy Use”),
establishes qualification requirements to applicants for activities related to atomic energy use,establishes the list of documents necessary to get the license.
Basic rules and regulations for radiation safety are listed below.
 The General Rules of Permits Granting to the Staff or Works Execution in the Field of
Atomic Energy Use RD-II-023-10
 Sanitary and Hygiene Requirements for Radiation Safety SGTORB-203
 The Radiation Safety Standards NRB-99
 Structure and System (Regulatory organizations)
Committee’s staff number is 24 persons including the Committee`s Chairman and two his
Deputies. There are three departments in the Committee– Department of Supervision and Analysis,
Licensing Department and Department of Material Control and Nuclear Security.
1.2 Outline of Radiation Facilities and Radiation sources
1.2.1 Number of specialists and workers in related organizations
The number of people working with radiation related industry in Australia is difficult tocorrectly define now.
1.2.2 Number of radiation facilities including related facilities

National Nuclear Center (NNC) was created by presidential decree in May 1992. The NNC ischarged with conducting research on the peaceful use of nuclear energy and radiation safety and isalso responsible for evaluating the consequences of nuclear tests at the now-closed Semipalatinsk
Test Site. All nuclear research reactors in Kazakhstan are under the jurisdiction of the NNC. NNC
oversees the following four institutes:

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)

a.
b.
c.
d.

Institute of Nuclear Physics: Includes the VVR-K research reactor in Alatau;
Institute of Atomic Energy: Includes the IVG-1M, non-operational RA, and IGR
research reactors at the former Semipalatinsk Test Site;
Institute of Geophysical Research;Institute of Radiation Safety and Ecology.

The pool type reactor on the thermal neutrons VVR-K, The heat-carrier, moderator and areflector  demineralized water. It was put into operation in 1967, it worked on thermal capacityof 10 MWt till 1988 without deviations from the normal modes. From 1988 to 1998 works onsafety strengthening in conditions of high seismicity (calculations and substantiations,strengthening of designs, duplication of the systems responsible for the safety, registration of the
new documentation) have been spent. By the configuration change of the active zone, the thermal
capacity has been reduced to 6 MWt without loss of neutron flows.
Water-cooled reactor IVG.1M is an upgraded version of high-temperature gas-cooled reactor
IVG.1 commissioned in 1975 and initially intended for of fuel pins and NJP FA tests. During
updating gas-cooled reactor core was replaced by water-cooled one.
Impulse research reactor IGR is high-temperature self-quenched uranium-graphite
homogeneous thermal neutron reactor. Today IGR Reactor is used for test conduction in supportof concept of controlled fuel melt moving into the Fast reactors to prevent re-criticality at severe
core meltdown accidents.
Spent IRAS repository sole in Kazakhstan was installed in 1995. The repository allowed thelong-term safe storage (about 50 years), handling and disposal of spent IRAS, widely applied inindustry, science, medicine etc.
The repository is located on complex research reactor “Baikal-1” on the territory of former
Semipalatinsk Test Site. Complex “Baikal-1” is situated at 75 km from nearest inhabited locality.
The complex “Baikal-1” is bounded by protective perimeter, provided with up-dated physicalprotection and guarded by forces of Ministry of Internal Affairs RK.
Spent ionizing radiation ampoule sources, accepted for long-term storage from different
establishments and enterprises in Kazakhstan, are transported in protective containers by
special-purpose vehicles. Spent IRAS are extracted from protective containers, dismantled in hot
cell and enclosed in steel casing, which is then sealed. Filled casing is loaded into repository celland covered by ferroconcrete 40-ton lid. For transportation and shifting the special-purpose
equipment, including the frame crane with load capacity of 125 tons is used. Permanent
radiation monitoring is carried out on the territory of complex “Baikal-1”.
The repository allows to improve the ecological environment in many regions of Kazakhstan
and revive the cancer detection centers. By now over 40000 spent IRAS, including 30 oncologicalones over 2000 Cu each are accepted.
After shutdown of BN-350 reactor facility (MAEC site, Aktau), the issue of packing anddisposal of assemblies of spent nuclear fuel (SNF) is arisen for the Government of Kazakhstan.
Complex of research reactor (CRR) “Baikal-1" situated at 75 km from Kurchatov was chosen
by the RK Government to locate there long-term spent nuclear fuel storage (LTSNFS) placed inpackaging storage sets (PSS). USA suggested to use eight-seat ferroconcrete duel-use casks(DUC). Spent fuel will be placed into the 60 containers. Containers will be shipped by railtransport.

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)

RD department developed construction of SNF handling site including transfer site andstorage site. The main requirements to the repository and functional area are the following:- capacity of the storage site - 60 PSS upright;- unloading of the duel-use casks from highway freighters;- DUC tipping to the vertical position;- PSS extraction from the protective casing;-placement of PSS with SNF for the storing;- long-term storage of PSS with SNF;
- provision with power resources, physical protection system and supervisory control
system.
1.2.3 Activity and number of radiation sources and generators
Number and activity of sources in use now clarifies. After analyzing and summarizing theinformation will be presented.
1.2.3.1 Future plans and issues to be solved

A Feasibility Study for the project “Creation of the radiation protective chamber and thelong-term storage facility of SRW (solid radioactive wastes) at CRR “Baikal-1”” IAE NNC RK isdeveloped to increase the volume and nomenclature of RAW accepted for processing and storage.
1.3 Education and Training
The radiation workers and the personnel having access to Radiation Facilities shall takeappropriate radiation protection training courses in both the theoretical and practical aspects toacquire radiation-handling skills needed for radiation worker, or for access to controlled areas.
1.4 Standardization on radiation and radioactivity
IAE NNC RK metrology laboratory was officially recognized by authorized state
governmental agency as qualified and authorized legal entity to implement the prescribed
metrological examinations.
The laboratory has a right to implement the following metrological efforts:
 instrumentation checkup in compliance with licensing spheres (heat, electrical, radio, physicaland linear-angular engineering , ionizing radiation);
 instrumentation maintenance;
 metrological examination of technical and design documentation.
The most popular metrological services, introduced by Institute’s metrology laboratory, amid
Kazakhstan’s enterprises is ionizing radiation instrumentation checkup.
Representation, storage and transfer of unit sizes in metrology laboratory are carried out bymeans of working and reference standards and standard samples (measures).
All working standards and standard samples (measures) are checked (assessed) at certain
interval before usage.
Part 2. Status of Radiation Safety Management
2.1 Radiation safety management in various RI usage
2.1.1 Radiation Safety Management System
The management of radiation safety within various radiation facilities is governed by the88

FNCA Consolidated Report on Radiation Safety (Kazakhstan)specific standards, codes and guides.
Basic List of normative technical documents of Atomic Energy Committee related to fuel andRadiation safety Use in RK:• Nuclear safety rules for storage and transportation of nuclear-hazardous fissile materials,
PBYa-06-09-90• Safety rules for storage and transportation of nuclear fuel at nuclear power facilities,
PNAE G-14-029-91• Basic industrial nuclear safety rules for utilization, processing, storage and transportationof nuclear hazardous fission material, PBYa-06-00-96• General regulations for safety of research reactors during their design, construction andoperation, OPB IR-94, PNAE G-16-34-94• Technical requirement “Nuclear and radiation safety”, adopted by the Government
Decree, July 30, 2010
• Technical requirement “Nuclear and radiation safety of NPP”, adopted by theGovernment Decree, July 1, 2010
• Technical requirement “Nuclear and radiation safety of research nuclear facilities”,
adopted by the Government Decree, July 1, 2010•

Sanitary rules for radioactive wastes management SPORO-97
No. 5.01.011-97

2.1.2 Radiological Protection for Radiation Worker
Radiation Protection of workers has to be monitored to make sure that the total amount of
external and internal exposure doesn’t exceed yearly limit of effective dose by personal adosimeter and regular medical check in accordance with the applied regulations.
 Table 1: Radiation dose limits for radiation worker

Application
Effective dose

Dose limit
Occupational
Public20 mSv per year, averaged 1 mSv in a year, averaged
over a period of 5 consecutive over a period of 5
calendar years but not more consecutive calendar years
than 50 mSv per year
but not more than 5 mSv
per year

Annual equivalent dose in
the lens of the eye
150 mSv
the skin
500 mSv
the hands and feet
500 mSv

15 mSv
50 mSv
50 mSv

2.1.3 Radiological Protection for Radiation Area
Work processes and areas are designed to keep radiation exposure to a minimum. Where thepotential for exposure to radiation or contamination still exists, shielding and mechanicalventilation are employ to minimize the dose received. Areas are classified according to thepotential radiation and contamination level.

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)

2.1.4 Radiological Protection for the Public
Annual dose limit (1mSv/y) for the public is prescribed by the regulation as shown in Table 1
to ensure the protection of the public against radiation from RI in Kazakhstan.
2.1.5 Radiation Emergency Preparedness
Organizations, individuals conducting radiation activities shall develop their plans forradiation and nuclear incident response.
One important element in the investigation and emergency response is the radiation
monitoring, which pulled a problem in the following:- Assessment of effects of ionizing radiation on personnel and individuals from the population;- Determination of levels of environmental pollution, equipment, clothing, industrial andresidential premises.
Particular attention should be paid:- Choice and optimal use of dosimetric and radiometric equipment;- The choice of modes of operation of radiation equipment, the establishment of the victim's
location in relation to the radiation source, during his stay in the radiation field (to simulate aradiation accident);- On the amount of radiation control, depending on group accident.

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FNCA Consolidated Report on Radiation Safety (Malaysia)

7. Malaysia
Part 1. Use of Radiation Sources and Radiationエラー! ブックマークが定義されていません。
1.1 General .......................................... エラー! ブックマークが定義されていません。
1.1.1 Legislative framework and policy for radiation safetyエラー! ブックマークが定義されていません。
1.1.2 Structure and System (Regulatory organizations)エラー! ブックマークが定義されていません。
1.2 Outline of Radiation Facilities and Radiation sourcesエラー! ブックマークが定義されていません。
1.2.1 Number of specialists and Workers in related organizationsエラー! ブックマークが定義されていません。
1.3 Education and Training.................... エラー! ブックマークが定義されていません。
1.3.1 Radiation Industry usage ............... エラー! ブックマークが定義されていません。
1.3.2 Radiological protection ................. エラー! ブックマークが定義されていません。
1.4 Standardization on radiation and radioactivityエラー! ブックマークが定義されていません。
1.4.1 External radiation and its personnel dosimetryエラー! ブックマークが定義されていません。
1.4.2 Calibration Facilities ..................... エラー! ブックマークが定義されていません。
Part 2. Status of Radiation Safety Managementエラー! ブックマークが定義されていません。
2.1 Radiation Safety Measurement in Various Radioisotope Usagesエラー! ブックマークが定義されていません。
2.1.1 Radiation Safety Management Systemエラー! ブックマークが定義されていません。
2.1.2 Radiological Protection for Radiation Workersエラー! ブックマークが定義されていません。
2.1.3 Radiological Protection for Radiation Areaエラー! ブックマークが定義されていません。
2.1.4 Radiological Protection for the Publicエラー! ブックマークが定義されていません。
2.1.5 Radiation Emergency Preparedness エラー! ブックマークが定義されていません。
2.2 Radiation Safety Management in Research Reactorエラー! ブックマークが定義されていません。
2.2.1 Introduction ................................. エラー! ブックマークが定義されていません。
2.2.2 RTP Technical Specifications ........ エラー! ブックマークが定義されていません。
2.2.3 Safety Objective ........................... エラー! ブックマークが定義されていません。
2.2.4 Organisation and Management of Safetyエラー! ブックマークが定義されていません。
2.2.5 Safety Analysis Report.................. エラー! ブックマークが定義されていません。
2.2.6 Quality Assurance Programme ...... エラー! ブックマークが定義されていません。
2.2.7 Radiation Protection Programme ... エラー! ブックマークが定義されていません。
2.2.8 Emergency Preparedness and Responseエラー! ブックマークが定義されていません。
2.2.9 Operation and Maintenance........... エラー! ブックマークが定義されていません。
2.2.10 Reactor operation supervisors, radiation protection supervisors and traineesエラー! ブック
マークが定義されていません。

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FNCA Consolidated Report on Radiation Safety (Malaysia)

2.2.11 Regulations and Licensing........... エラー! ブックマークが定義されていません。
2.2.12 Peer Review ............................... エラー! ブックマークが定義されていません。
2.3 Radiation Safety Management in Radioactive Waste Managementエラー! ブックマークが定義されていません。
2.3.1 Introduction ................................. エラー! ブックマークが定義されていません。
2.3.2 Radiation Safety Management in Transport of Radioactive Materialエラー! ブックマークが定義されていません。

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FNCA Consolidated Report on Radiation Safety (Malaysia)

7. Malaysia
Part 1. Use of Radiation Sources and Radiation
1.1 General
1.1.1 Legislative framework and policy for radiation safety
Control over the use of radioactive substances in Malaysia began in 1968 when the Parliament
passed the Radioactive Substances Act 1968. Due to rapid development of atomic energy
activities in Malaysia which requires more effective control, inspection and enforcement, theAtomic Energy Licensing Bill was drafted and was passed by Parliament in April 1984 as theAtomic Energy Licensing Act (Act 304).
Fig. 1: Hierarchy of Legal System

There are three main regulations made under the Act 304 namely:
Radiation Protection (Licensing) Regulations 1986;
Radiation Protection (Basic safety Standard) Regulations 1988;
Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010;
Radiation Protection (Transport) Regulations 1989
1.1.2 Structure and System (Regulatory organizations)
In line with Section 3 of the Act 304, the Atomic Energy Licensing Board (AELB) wasestablished under the Prime Minister’s Department on 1 February 1985. The AELB acts as an
enforcement body for the implementation of the Act. However on 27 October 1990 the Board wasplace under the Ministry of Science, Technology and Innovation (MOSTI).
The functions of AELB as stated in Act 304 are as follows: To advise the Minister and the government of Malaysia on matters relating to the Atomic
Energy Licensing Act 1984 and developments pertaining thereto with particular reference

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FNCA Consolidated Report on Radiation Safety (Malaysia)

to the implications of such developments for Malaysia;
 To exercise and supervision over the production, application and use of atomic energy
and matters incidental thereto ; To establish, maintain and develop scientific and technical co-operation with such otherbodies, institutions or organizations in relation to nuclear matters or atomic energy as theBoard thinks fit for the purposes of the Atomic Energy Licensing Act 1984 ; Where so directed by the government of Malaysia, to perform or provide for the
performance of the obligations arising from agreements, conventions or treaties relating
to nuclear matters or atomic energy to which Malaysia is a party where such agreements,
conventions or treaties relate to the purposes of the Atomic Energy Licensing Act
1984 ;and To do such other things arising out of or consequential to the functions of the Board
under the Atomic Energy Licensing Act 1984 which are not inconsistent with the
purposes of this Act, whether or not directed by the Minister.
Since the enforcement of the Act 304, a major part of the responsibility was under thejurisdiction of the Atomic energy licensing Board. However, the control of application in medical
purposes is under jurisdiction Director General of Health, Ministry of Health.
1.2 Outline of Radiation Facilities and Radiation sources
1.2.1 Number of specialists and Workers in related organizations
In Malaysia, the number specialists and workers involved with radiation related industry are
maintained by the AELB and MOH. However, the exact total number of workers involved withradiation is very difficult to define.
1.3 Education and Training
1.3.1 Radiation Industry usage
Under the Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010, alllicensees are required to have a Radiation Protection Officer (RPO). RPO is defined as a technicallycompetent person approved and recognized by the regulatory body. The RPO shall go through special
radiation protection course at recognized institutions and shall pass an examination before can beapproved as RPO by the regulatory body.
The Licensee is also required to employ and engage well trained radiation workers. The workers arealso shall be provided an appropriate retraining for updating their skill and knowledge. Industry related
occupations include industrial radiographers, borehole loggers, industrial gauges user, seller andtrader, radiation source testers and persons servicing, installing, commissioning, maintaining,
repairing or manufacturing radiation sources and equipment, lecturers and technician at higher
leaning institutions, researchers at research institutes etc.
Health related occupations include medical practitioners, dental practitioners, veterinary
surgeons, diagnostic radiographers, radiation therapists, nuclear medicine technologists, healthand medical physicists.

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FNCA Consolidated Report on Radiation Safety (Malaysia)

1.3.2 Radiological protection
Numerous companies, institutes and universities provide education and training in radiation
safety, radiological protection and related courses. There are approximately seven providers andaround 100 radiation safety training courses covering subjects including general radiation
awareness, radiation protection, use of radionuclides, use of gauges, transport, and use of radiation
in medical procedures.
1.4 Standardization on radiation and radioactivity
1.4.1 External radiation and its personnel dosimetry
External radiation quantity can be measured in terms of exposure, air kerma, absorbed dose,
dose equivalent, ambient dose equivalent and directional dose equivalent by using radiation
measuring instruments. Various kinds of radiation measuring instruments such as survey meters,
area monitors, personal dosimeters, contamination monitoring instruments are used in theradiation facilities for radiation protection purposes. For implementation of the proper monitoring,radiation monitoring survey meters e.g. ionization chambers, Geiger-Muller (GM) counters andscintillation counters should be calibrated in terms of dose equivalent quantities. Area dosimetersor dose ratemeters should be calibrated in terms of the ambient dose equivalent, H*(10), or the
directional dose equivalent, H’(0.07). In radiotherapy centres, the radiation dosimeters arenormally used for determinations of the output of Cobalt-60 teletherapy units and medical linear
accelerators (linacs) should be calibrated in terms of exposure, air kerma or absorbed dose towater. Radiation measuring instruments need to be calibrated to ensure that they give accurate andcorrect reading with a certain uncertainties and to comply with the regulations imposed by therelevant authority. They should be calibrated annually or after major repair. In Malaysia,
calibration of radiation measuring instruments is a legal requirement under the Radiation
Protection (Basic Safety Standard) Regulation, 1988[8]. The SSDL-Nuklear Malaysia wasestablished in 1980 and a member of the IAEA/WHO Network of SSDLs. The laboratory had
acquired the status of national standard laboratory with the basic aim of improving accuracy inradiation dosimetry in the country. It is also the national focal point for the calibration of radiation
measuring instruments used in radiation protection and radiotherapy. More than 1500 radiation
instruments are normally calibrated every year. The laboratory has also the responsibility to ensurethat the calibration services provided by the laboratory follow internationally accepted
metrological standards. This is achieved by calibrating the protection and therapy levels
dosimeters belongs to SSDL-Nuklear Malaysia against the Primary Standard Dosimetry
Laboratories (PSDLs) or the International Atomic Energy Agency (IAEA) or by participating theinternational comparison on dosimetry measurements.
1.4.2 Calibration Facilities
1.4.2.1 Irradiation facilities.
The calibration of radiation instruments used for radiation protection and radiotherapy
purposes requires appropriate irradiation facilities capable of providing air kerma rates up to
approximately 1Gy/min. The SSDL-Nuklear Malaysia has four irradiation rooms or bunkers toaccommodate radiation sources and to perform calibration of radiation protection survey
instruments and therapy level dosimeters. The dimensions of the irradiation rooms wereapproximately 9m x 4.8m x 3.2m high. The floor, walls and ceiling are concrete. The design of the95

FNCA Consolidated Report on Radiation Safety (Malaysia)

irradiation rooms are in accordance with the relevant national and international safety regulations.
The shielding of the rooms is sufficient to ensure that the radiation doses to the staff and the public
are kept as low as reasonably achievable and that the given dose limits are not exceeded. The
irradiation rooms are equipped with the radioactive and x-ray sources that are operated remotelyin the control room. This room also contains monitors coupled to video cameras in the irradiation
rooms. The rooms are provided with the calibration benches running on a pair of rails to carry out
the measurements of radiation at various distances from the sources and calibrate the radiation
measuring instruments. The ionization chambers or radiation survey instruments are positioned on
the calibration benches where they can be moved into a required distance from the source. Their
position is fixed at the calibration distance using a telescope or laser. Laser alignments are also
installed at each irradiation room to ensure that the radiation survey meters and dosimeters areplaced in the centre of the radiation beam during the measurements. The irradiation rooms are also
provided with appropriate safety equipment and accessories such as warning light for each
irradiation unit, door interlocks and continuously operating radiation monitors.
1.4.2.2 Radiation sources.
(i) X-radiation.
Calibration at photon energies below 300 keV is usually carried out using an x-ray system.
SSDL-Nuklear Malaysia has created a series of x-ray beam qualities which were selected to matchthe beam qualities offered by the International Bureau of Weight and Measures (BIPM) and basedon ISO Narrow Spectrum Series. The Yxlon constant potential x-ray systems type MG 325 with a
320 kV tube is used to generate ISO narrow spectrum series x-ray reference radiation for thecalibration of radiation protection instruments. Their beam characteristics are shown in table 1,
where the values of the mean energies have been adopted from the ISO document. X-rays
generated between 100 kV and 250 kV in accordance with the BIPM therapy qualities are used forcalibration of therapy level dosimeters.
Table 1: ISO Narrow Spectrum Series X-ray Beams at the SSDL-Nuclear Malaysia

Radiation
quality
N-40
N-60
N-80
N-100
N-120
N-150
N-200
N-250
N-300

Mean
energy
[keV]
33
47
65
83
100
117
164
207
248

Tube
potential
[kV]
40
60
80
100
120
150
200
250
300

Al
4.0
4.0
4.0
4.0
4.0
4.0
4.0
4.0
4.0

Additional filtration
[mm]
Cu
Sn
0.2
0.6
2.0
5.0
5.0
1.0
2.5
2.0
3.0
2.0
3.0

96

Pb
1.0
3.0
5.0

HVL
[mm]
Cu
0.09
0.25
0.59
1.15
1.78
2.58
4.13
5.34
6.33

FNCA Consolidated Report on Radiation Safety (Malaysia)

Table 2: Therapy Qualities X-ray Beams at the SSDL-MINT

Tube potential[ kV ]
100
135
180
250

Additional filtration [mm]
Al
Cu
3.5
1.0
0.3
1.0
0.6
1.0
1.6

HVL [mm]
Al
4.05
-

Cu
0.50
1.01
2.51

(ii) Gamma radiation.
Radionuclide sources are used to perform calibration at photon energies above 300 keV. There
are several gamma sources i.e. Caesium-137, Cobalt-60 and Americium-241 with different
activities are available to provide radiation standards for protection and therapy level dose rates.
Two irradiation rooms are equipped with two collimated gamma irradiators model OB 85 which
consists of 137Cs (740 GBq) and 60Co (37 GBq) and two panoramic gamma irradiators model OB
34. The panoramic gamma irradiator contains a total of seven 137Cs and 60Co gamma sources withactivities ranging from 3.7 MBq to 7.4 GBq that produce uncollimated radiation fields. Table 3
shows the specification of protection level gamma sources used to calibrate radiation survey
instruments. The reference gamma radiation fields are determined in terms of air kerma rate. A
teletherapy 60Co unit model Eldorado 8 is used to provide national standards for air kerma andabsorbed dose to water at therapy level and calibration service for therapy level dosimeters.
Table 3: Protection level gamma sources

Gamma Nuclide
irradiator
OB 34
Cs-137
Co-60
OB 85

OB 6
-

Activity range
7.4MBq-7.4GBq

No. ofsource4

Cs-137

3.7MBq-370MBq
740 GBq

3
1

Co-60

37 GBq1

Cs-137
Am-24174 GBq11.1 GBq

1
1

Covered air kerma
Sourcerate range
distance [m]0.5 – 2.5
0.49 Gy/h - 1.59
mGy/h
0.5 – 2.5
0.29 – 38.94 Gy/h
16.53 Gy/h- 150.48
mGy/h
5.76 Gy/h – 5.54
mGy/h
0.22 – 14.56 mGy/h
5.08 – 119.92 Gy/h

0.5 – 5.0
0.5 – 5.0
0.5 – 4.0
0.4
–
2.0

(iii) Beta radiation
The beta radiation sources of the Pm-147, Kr-85 and Sr-90/Y-90 nuclides of the PTB Beta
Secondary Standard (BSS 2) developed by the Physikalisch-Technische Bundesanstalt (PTB),
Germany are used to calibrate radiation survey instruments. The radiation qualities are incompliance with the series of standards ISO 6980. The sources are calibrated by PTB at the
specified distances in terms of absorbed dose rate to tissue surface, directional dose equivalent rate
and personal dose equivalent rate. The dose rate at the calibration distance is between 7 Gy/s and38 Gy/s. The irradiation procedure is controlled by a personal computer which stores thecalibration data for the source used. The specifications of beta sources have been summarized in

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FNCA Consolidated Report on Radiation Safety (Malaysia)

table 4.
Table 4: Beta Secondary Standard Sources.

SourceRadionuclide
Nominal activity
Beam flattening filter
Mean beta energy (MeV)
Calibration distance (cm)Reference dateHalf-life (years)

1
Pm-147
3.7 GBq
Yes
0.06
20
07.02.2003
2.62

2
Kr-85
3.7 GBq
Yes
0.24
30
27.02.2003
10.72

3
Sr-90/Y-90
460 MBqNo
0.811, 20, 30 & 50
28.03.2003
28.8 years(iv) Neutron
The collimated neutron calibrator model OB 26 manufactured by Buchler GmbH, Germany
which consists of 185 GBq Americium-241/Beryllium neutron source is available to carry out
calibration of neutron survey instruments and personal dosimeters. The neutron emission rate
quoted by manufacturer was 1.1 x 107 n/s on July 20, 1984.
1.4.2.3 Dosimetric equipments
The SSDL-Nuklear Malaysia is equipped with secondary standard dosimeters and working
standard dosimeters to provide exposure and air kerma standards used for calibrating radiation
survey instruments while the air kerma and absorbed dose to water standards for calibrating
therapy level dosimeters. The secondary standards for radiation protection are based on 1,000
cm3 and 10,000 cm3 spherical ionization chambers, LS-01 and LS-10 designed and manufactured
by PTW, Germany and the Austrian Research Centre, Austria respectively. The chambers arecalibrated in terms of air kerma at 137Cs, 60Co and a number of x-ray beam qualities at the IAEA
Dosimetry Laboratory and the Austrian Research Centre Seibersdorf. A 0.6 cm3 ionizationchamber NE 2571 has been selected as reference chamber for the calibration of therapy level
dosimeters. The chamber had been calibrated in terms of absorbed dose to water at 60Co and air
kerma at 60Co and x-ray beam qualities at the IAEA Dosimetry Laboratory. The ionization current
from the ionization chambers is measured with a PTW-Unidos Universal Dosimeter and Digital
Currentintegrator DCI 8500 with calibration is traceable to the National Metrology Laboratory,
SIRIM Berhad. The leakage current for the system ionization chamber plus electrometer isconsidered negligible. The stability of the chamber plus electrometer system is checked at regularintervals using a 90Sr and 241Am check source. Working standard dosimeters used for protection
and therapy levels at SSDL are calibrated against secondary standard dosimeters. They areroutinely used for the calibration of radiation protection survey instruments and therapy level
dosimeters.
1.4.3 Calibration of Radiation Instruments
1.4.3.1 Radiological protection instruments.
Radiation protection survey instruments such as ionization chamber, Geiger-Muller counter,
scintillation counter and solid state detector are calibrated in terms of exposure, air kerma,
dose equivalent and ambient dose equivalent as well as directional dose equivalent. Reference
photon radiation selected from ISO Standard 4037-1[9] are used for calibration of radiation survey
instruments and for determination of their energy response. For the x and gamma radiation

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qualities, the conversion coefficients given in ISO Standard 4037-3 were used for conversion fromair kerma to ambient dose equivalent, H*(10) or directional dose equivalent, H’ (0.07). Reference
conditions are temperature = 20.0 0C, pressure = 1013.25 mbar and relative humidity (RH) = 50 %.
H*(10) and H’(0.07) are new operational quantities for area monitoring for external radiation
sources introduced by ICRU Report 39 and intended mainly for the measurements of strongly
penetrating and weakly penetrating radiations respectively. Calibrations are performed either by
the substitution method (comparing the response of the instrument to be calibrated with that of areference standard instrument) or simultaneous method (both instrument to be calibrated andreference standard instrument are placed in the radiation beam at the same time and irradiatedtogether). These methods are normally used when the radiation survey meters are calibrated at
x-ray beams. Calibration is performed in a known radiation field when the survey meters arecalibrated against gamma, beta and neutron beams. Standardization of 137Cs, 60Co, and 241Am
gamma sources (protection level) at various distances using reference standard dosimeters are
performed once a year with accuracy better than  2%. Calibration with beta radiation is
performed using beta secondary standard sources which the absorbed dose rates at particulardistances of each sources i.e. 90Sr/90Y, 85Kr and 147Pm have been determined by the PTB, thenational standard laboratory of Germany or by using PTW extrapolation ionization chamber.
Portable survey instruments are calibrated at least at one point on each measuring range i.e. atapproximately half of their full scale value or in each decade for an instrument with a logarithmic
scale or with digital indication. The calibration factor or coefficient is defined as the ratio of thevalue of stated true exposure or dose equivalent rate at the position of the centre of the detector in
the absence of the instrument to the instrument indication. The stated true exposure or dose
equivalent rate was measured using reference standard dosimeters.
1.4.3.2 Therapy level dosimeters
Radiotherapy centres must possess an ionization chamber with a calibration factor or
coefficient traceable to a secondary standard dosimetry laboratory. SSDL has provided air kerma
calibration coefficient, NK or exposure calibration coefficient, NX and absorbed dose to water
calibration coefficient, ND,W at a single high energy photon beam which is normally refer to 60Co
gamma rays.
The ionization chamber is calibrated in air with build-up cap. The reference point of thechamber is positioned on the central axis of the beam so that the chamber axis was perpendicular
to the central axis of the beam. Source to the chamber distance(SCD) is 100 cm and the field size(FS) at SCD was 10 x 10 cm2 in the 60Co gamma beam or focus to the chamber distance (FCD) is
100 cm and the field size is diameter ( ) 10 cm in x-ray beam. The air kerma calibration factor Nk[mGy/nC] of the chamber was determined as the ratio of the air kerma standard, Kair obtained by
the SSDL standard and the electrical charge Q (nC) produced in the chamber under calibration.
The charge is measured by the electrometer belongs to the users. The results of the calibration
normalized to the standard atmospheric conditions (i.e. T = 20 OC, P = 1013.25 mbar and R.H. =50%). The calibration is performed by the substitution method using the SSDL reference standard
chamber.
1.4.4 Accreditation of Laboratory
The laboratory is well known as the national focal point for the calibration of radiation
measuring instruments used in radiation protection and radiotherapy. To maintain the radiation

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dosimetry standard in accordance with an international standard, a comprehensive quality
assurance programme based on the ISO/IEC 17025 was adopted and implemented. In July 23rd
2004, the SSDL-Nuklear Malaysia has been accredited as a calibration laboratory for radiation
survey meters and therapy dosimeters by the Department Standard of Malaysia (The Malaysianaccreditation body) under the Laboratory Accreditation Scheme of Malaysia (SAMM). The
scheme would provide solid foundation for the SSDL-Nuklear Malaysia to earn strong status instrengthening and maintaining public and customers confidence in the measurements of ionizing
radiation.

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Measurement in Various Radioisotope Usages
2.1.1 Radiation Safety Management System
The management of radiation safety within various radiation industries is governed by theregulator according to the regulations, order, licence conditions, code of practice, guideline,
established under the Act 304 and from time to time regulatory directive published by the AELB.
These include all radiation management considerations for research, industrial and medical related
facilities as follows: Radiation Protection (Transport) Regulations 1989;
 Radiation Protection (Basic safety Standard) Regulations 1988;
 Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010;
 Guidelines on Radiological Monitoring for Oil and Gas Facilities Operators Associatedwith Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM).
 Code of Practice on Radiation Protection of Industrial Radiography.
 Guidelines for Testing X-Ray Apparatus.
 Code of Practice on Radiation Protection of Non Medical Gamma & Electron Irradiation
Facilities
 Code of Practice on Radiation Protection Relating to Technically Enhanced Naturally
Occurring Radioactive Material (TENORM) in Oil and Gas Facilities
 Guidelines on Radiological Monitoring for Oil and Gas Facilities Operators Associatedwith Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM)’
LEM/TEK/30);
 Guidance on Scheme towards the Recognition of a Radioactive Laboratory by Atomic
Energy Licensing Board.
 Guidelines for Decommissioning of Facilities Contaminated with Radioactive Materials.
 Guideline on Preparation of Radiation Protection Programme for Industrial Radiography(LEM/TEK/45 Part D) Guideline on Preparation of Radiation Protection Programme for Industrial Seller/Trader(LEM/TEK/45 Part A) Guideline on Preparation of Radiation Protection Programme for Nuclear Gauges(LEM/TEK/45 Part B) Guideline on Preparation of Radiation Protection Programme for Research Institute(LEM/TEK/45 Part C)100

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2.1.2 Radiological Protection for Radiation Workers
It has been recognised that exposure to at certain level can cause clinical damage to human tissues.
It is therefore essential that activities involving radiation exposure shall be subjected to certain standardsof safety in order to protect individual worker exposed to radiation. As such, all radiation industries
and facilities are required to implement ALARA concept limits possible detrimental effects arising fromoccupational radiation exposure. This concept can be achieved through: No practice within a practice should be authorised unless the practice produce sufficient benefit
to the exposed individuals or society avoidance of exposure, where practicable; use shielding to isolate of sources of radiation, where practicable, keep the distance by remote handling techniques; Use appropriate personal protective equipment whether deal with sealed or unsealed sources.
 Use fume hood if deal with volatile material or liquid.
Under the Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010
radiation dose limitation for worker and public are as stated in Table 5.
Table 5: Radiation Dose Limits

Application
Effective dose
Lens of the eye
Skin
Hands and feetOccupational

Annual Dose limit
Public

20mSv
150mSv
500mSv
500mSv

1mSv
15mSv
50mSv
-

Apprentices andstudents
6mSv
50mSv
150mSv
150mSv

2.1.3 Radiological Protection for Radiation Area
Radiation area programme should be established by the operator in the supervised area andcontrolled area. Monitoring of workplace areas is required to be performed by the operator under
supervision of radiation protection officer. The monitoring programme shall include— measurements of external radiation levels and contamination levels (where appropriate) at
specified places, times and frequencies at all appropriate locations so as to evaluate theradiological conditions in all work places; exposure assessments in controlled areas and supervised areas; assessment of the levels of radiation risks associated with an accident or emergency
situation;
2.1.4 Radiological Protection for the Public
The licensee whose radiation sources are under his responsibility shall ensure that exposure
attribute to the general public is optimised and shall not exceed the dose limits as stated in Table 1.
Therefore the licensee shall ensure that the public exposures be controlled in accordance with therequirement of the regulations and guideline.
The licensee is also shall be responsible for ensuring that the optimization process formeasure to control discharge of radioactive substances to the environment is comply with therequirement of the regulatory body taking into account exposure pathways, changes in the habitats

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or distribution of the population, modification of critical group or changes in environmental
dispersion conditions.
For visitors to enter controlled area, they must be accompanied by a person knowledgeable
about the protection and safety measures for that area. They also must be provided adequate
information and instruction before they enter a controlled area so as to ensure appropriate
protection to them
2.1.5 Radiation Emergency Preparedness
The licensee shall make suitable arrangements to prevent as far as possible, any accident that
could reasonably be foreseen for any radiation source which is in his possession or under his
control, and to limit the consequences of any accident that occurs. It is obligatory requirement forthe operators to establish radiological emergency plan if it happen inside their premises.
The National Security Council (NSC) which is under the Prime Minister’s Department, is
responsible for managing the whole operation of nuclear and radiological emergency, whether it isa national, state or district level, if the emergency is considered a disaster. The AELB is a leadtechnical agency whereas Nuclear Malaysia will be called if there is a need for technicalassistance in handling the emergency. In the event of a radiological emergency the following plans
are in place: Radiological Emergency Response Plan (RAD Plan) Directive No 20 of National Security Council – The Policy and Mechanism on National
Disaster and Relief Management
 Convention on Assistance in the Case of Nuclear Accident and Radiological AccidentConvention on early Notification of a Nuclear Accident.
2.2 Radiation Safety Management in Research Reactor
2.2.1 Introduction
Malaysian Nuclear Agency or Nuclear Malaysia, which was established in early 1970’s, is an
institution that develops, promotes and enhances the peaceful uses of nuclear technology inagriculture, medical, manufacturing, industry, health and the environment. In order to enhanceresearch and development activities, a TRIGA MARK II research reactor, called Reaktor TRIGAPUSPATI (RTP), was built. It came into operation in 1982 and reached its first criticality on 28
June 1982.
The reactor was designed to effectively implement the various fields of basic nuclear scienceand education. It incorporates facilities for advanced neutron and gamma radiation studies as well
as for application, including Neutron Activation Analysis (NAA), Delayed Neutron Activation
Analysis (DNA), radioisotope production for medical, industrial and agricultural purposes,
neutron radiography and Small Angel Neutron Scattering (SANS).
2.2.2 RTP Technical Specifications

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RTP was supplied by General Atomicof the USA and installation programme
was started on 9 November 1981. RTP isa pool type reactor where the reactor coresits at the bottom of 7 metre highaluminium tank which is surrounded by abiological shielding made of high density
concrete (see Figure 2). The reactor uses
solid fuel elements in which azirconium-hydride
moderatorishomogeneously combined with enricheduranium. Demineralised water acts bothas coolant and neutron moderator, whilegraphite acts as reflector. The following are brief descriptions of RTP:










Type: TRIGA Mk II, pool type
Fuel: Uranium Zirconium Hydride Alloy
Coolant: Light Water
Moderator: Light Water
Reflector:
GraphiteControl Rods: Boron Carbide
Fig. 2: Nuclear Malaysia’s Reactor TRIGA PUSPATI (RTP)
Status: Operating
Operational Mode: Steady State (1MW)
Operation: 6hrs/day weekdays

2.2.3 Safety Objective
Since established, the promoting safety of RTP operation is a prime concern of the
management and the staff of Nuclear Malaysia. These include during operation, repair andmaintenance, radiation doses to workers, radioactive waste management and environmental
management. The fundamental safety objective is to protect people, both individually andcollectively (workers and public at large) and the environment from harmful effects of ionizing
radiation. However, this should been achieved without unduly limiting the operation of facilitiesor the conduct of activities that give rise to radiations risks. In order to achieve the fundamental
safety objective, Nuclear Malaysia has implemented the ten safety principles formulated byInternational Atomic Energy Agency (IAEA) on the basis of which safety requirements aredeveloped and safety measures are to be implemented.
2.2.4 Organisation and Management of Safety
2.2.4.1 Nuclear Malaysia’s Occupational Safety, Health and Environment Policy Statement
Nuclear Malaysia, an agency who responsible for the promotion, development and applicationof nuclear technology and nuclear related technology for the national development, is committed
to continually improve and prevent pollution, incidents, accidents and occupational illness in its
operation. This is the commitment of the management in ensuring safety at Nuclear Malaysia
complex. Toward this end, Nuclear Malaysia will:Comply with all applicable environmental, occupational safety and health, legal and otherrequirements.

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








Minimize release of pollutants to air, water, land and promote waste minimization throughreduction, recycling and reusing activities.
Optimize the use of materials and natural resources.
Ensure that all radiation exposures are kept as low as reasonably achievable.
Ensure that all other occupational hazards and risks are prevented, where practicable, andcontrolled and managed through the adoption of proper management measures.
Stress on environmental, occupational health and safety aspects in our facilities operation,equipment, field work, building construction and modification through appropriate
assessments at the planning stage.
Promote environmental, occupational health and safety awareness among employees,
contractors, vendors and visitors.
Ensure that all employees, contractor, vendors and visitors on site comply with Nuclear
Malaysia’s environmental, occupational health and safety requirements at all times.

This safety policy statement is displayed at all notices boards within the Nuclear Malaysia
premises to inculcate safety culture to all staff and contract workers, and to show that management
is serious in managing safety.
2.2.4.2 Safety Management System
In ensuring the above safety policy implemented in daily work, Safety, Health andEnvironmental Management System (SHE-MS) Committee was established in year 2005 toreview all aspects of safety, including occupational, nuclear and radiological safety. This
committee is responsible to report all safety activities in Nuclear Malaysia to the highest
management committee headed by the Director General. Safety Audit Team performs auditing
functions and reports its finding to the SHE-MS committee on a regular basis. For RTP, the set-upof organization safety management is shown in Figure 3.

OPERATION AND SAFETY MANAGEMENTREAKTOR TRIGA PUSPATI (RTP)
NUCLEAR MALAYSIA
INTERNATIONAL ATOMICENERGY AGENCY (IAEA)

DIRECTOR GENERALNUCLEAR MALAYSIA

DEPUTY DIRECTOR
GENERAL(Technical Services Program)

DIRECTORTECHNICAL SERVICEDIVISION

SAFETY & HEALTHCOMMITTEEMAJOR FACILITIESSAFETY SUBCOMMITTEE

DIRECTORRADIATION SAFETY AND HEALTHDIVISION.

MANAGERHEAD

HEALTH PHYSICSGROUPPHYSICAL SECURITYUNIT

NUCLEAR SAFETY
DEPARTMENTSAFEGUARDS
DEPARTMENTOPERATION
SAFETYMANAGERMECHANICAL AND
ELECTRICAL UNIT

MANAGERREACTOR FACILITYPHYSICALSECURITYSERVICESHEALTH &RADIATION
SAFETY SERVICES

SAFETYINSPECTION(INSARR)

SAFEGUARDSINSPECTIONSOPERATION AND MAINTENANCE
REAKTOR TRIGA PUSPATIMANAGERWASTEMANAGEMENTCENTRESAFETY INSPECTION &NUCLEAR MATERIALSSAFEGUARDS

Fig. 3: RTP Safety Management System

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LICENSING BOARD(AELB)

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The RTP is headed by a Reactor Manager whose is directly report to the Director of Nuclear
Power. To maintain high level of safety, the operation and maintenance of RTP are supported by
the other groups such as Radiation Safety and Health Division, Waste Technology Development
Centre, Mechanical and Electrical Unit and Physical Security Unit.
2.2.5 Safety Analysis Report
Safety analysis report (SAR) is an essential document when talking about safety in nuclear
installations. Nuclear Malaysia’s first SAR document for RTP was prepared in 1982. Since then,the document had not been revised until 2007 when the new SAR document was prepared inaccordance with the IAEA safety standards and recommendations [3]. The SAR document has
been submitted to the regulatory body for an approval. In preparing this document, Nuclear
Malaysia had engaged experts from abroad to help preparing the document because of lacking of
capability and expertise to do analysis especially on risk analysis.
2.2.6 Quality Assurance Programme
Quality Assurance Programme (QAP) is very important in running nuclear reactor and it is not
exceptional with RTP. QAP for RTP has been reviewed and approved by SHE-MS Committee lastyear and will be submitted to the regulatory body this year for their comment. Some of thecontent of the QAP are Operational Control, Emergency Response and Preparedness, Safety and
Health, Physical Security, Infrastructure Maintenance, Reactor Maintenance, Experiment andModification, Measurement and Monitoring Device Control, Human Resource Management,
Waste Management, Special Nuclear Material Counting Control and refuelling.
2.2.7 Radiation Protection Programme
Radiation exposure is set-out in the safety manual approved by the SHE-MS Committee. It isbased on the Radiation Protection (Basic Safety Standards) Regulations [2] and IAEA safety
documents. In the manual, radiation exposure is managed using radiation protection principles
such as policy on As Low As Reasonable and Achievable (ALARA), annual dose limit, annual
limit of intake (ALI), Derived Air Concentrations (DAC), classification of area, personal
dosimetry etc.
All radiation workers are provided with TLD badges for personal monitoring which areassessed on monthly basis. Staff working with unsealed sources or using hand on more of theirwork wear wrist and finger TLDs as well. On the other hand, area monitoring using TLDs is
performed at all control areas. Medical surveillance of radiation workers are also carried out atleast once in two years.
Environmental samples such as water, sediments, soils, vegetables from areas surrounding
Nuclear Malaysia complex are collected and analysed. Whilst external radiations from the nuclear
installation are monitored using TLDs which are changed on monthly basis.
2.2.8 Emergency Preparedness and Response
Emergency preparedness means being ready to reacts or response to a broad range of
emergency situations that can occur at anytime and anywhere. Widespread use of nuclear
technologies in application as diverse as industry, medicine, agriculture etc. in Malaysia, meansthat more possibility of accident can happen. In recent year, most countries including Malaysia arevery concern about emergencies arising from malicious use of radioactive material or ‘dirty
bomb’.

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In Nuclear Malaysia, emergency preparedness and response are given very top priority by the
top management. On-site Emergency Response Plan (ERP) is in place and recently has beenrevised. On the other hand the off-site emergency plan is under the jurisdiction of the regulatory
body which is the lead technical agency to handle any radiological emergency at national level
under the Directive No. 20, National Security Council. Emergency drill is performed at least twicea year. In year 2007, two exercises have been done where the first exercise was done at RTP
building and the second was done at the Waste Treatment Centre.
2.2.9 Operation and MaintenanceWithout a doubt, a good design, manufacture and construction of reactor are pre-requisites forhigh levels of safety. However, the ultimate responsibility for safe operation lies with the operatingorganization (Safety Principles 1). Therefore, Nuclear Malaysia is really emphasized on this issue.
RTP reactor building, equipment and facilities are well maintained, generally clean and tidy and ingood condition [4]. The annual and semi-annual maintenance are carried out in June andDecember respectively. Any change in operation and maintenance plan must be approved byReactor Supervisor. However any unplanned maintenance works must be approved by the Reactor
Manager upon recommendation of the Reactor Supervisor.
2.2.10 Reactor operation supervisors, radiation protection supervisors and trainees
As safety is a prime concern of Nuclear Malaysia, therefore education and training on nuclear
and radiological safety to staff are very important. For a new staff, they are required to attend an
induction course while the other staff are encouraged to attend a radiation safety awarenesstraining course conducted by Nuclear Malaysia. Nuclear Malaysia is also sent their staff to, either
local institutions or a broad for updating their skills and knowledge.
For a reactor operator, there is a training programme which is based on the guidelines issued
by the AELB where Nuclear Malaysia is responsible for conducting the course while theexamination and issuance of operator licence are managed by the AELB. The reactor operator
licence can only be renewed after the licensed operators have successfully undergone a refresher
course.
2.2.11 Regulations and Licensing
Principle 2 of the safety objectives is clearly stated that there shall be an independent
regulatory body in each country to control and supervise all atomic energy activities. Therefore, tomaintain independency, Nuclear Malaysia is licensed by the Atomic Energy Licensing Board(AELB), which is independent body established under the Atomic Energy Licensing Board 1984
(Act 304). This is to ensure that the safety is kept in high standard and consistent with the IAEA’s
nuclear safety standards. The AELB regularly inspects RTP to ensure that all requirements under
the law and regulations are complied.
Alongside inspections, yearly dialogue and direct meeting between the Nuclear Malaysia and
AELB are made to exchange information and resolution of issues raised. This meeting isalternately chaired by the Director General of AELB and Director General of Nuclear Malaysia. A
part of that, the AELB is reviewing their regulations and guidelines related with nuclear safety inaccordance to the latest IAEA’s safety standards and guidelines.
2.2.12 Peer Review
Peer review is necessary to achieve and maintain a high level of nuclear safety and safety

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culture. For this purpose, international peer review group on safety culture and nuclear safety arewelcome. In 2005, the implementation of nuclear safety culture at RTP has been reviewed byForum for Nuclear Cooperation in Asia (FNCA) review team. Recommendations from this teamhave been implemented.
2.3 Radiation Safety Management in Radioactive Waste Management
2.3.1 Introduction
Nuclear Malaysia is committed to minimize release of pollutants to air, water, land andpromote waste minimization through reduction, recycling and natural resources. All precautions
are taken into account to minimise the generation of unnecessary activation radionuclides tominimise waste generation. This is evaluated when request for irradiation is received.
There also has a specific procedure for collection, control and treatment of radioactive waste
activities as specified in the Nuclear Malaysia’s safety, health and environment manual. The Waste
Treatment Centre, an organization within Nuclear Malaysia, is gave responsibility to manage
radioactive waste and chemical waste. In this centre, radioactive wastes are categorized andseparated based on their types, solid or/and liquid and according to the standard classification ofradioactive waste established by the IAEA. With respect of spent fuel, until now, Nuclear
Malaysia has no spent fuel at all. However, the RTP was designed in such a way that it can beused as a storage facility for spent fuels before these spent fuels are sent back to the supplier.
2.3.2 Radiation Safety Management in Transport of Radioactive Material
The regulation of the transport of radioactive material in Malaysia has, for many years, been
based on international requirements published by the International Atomic Energy Agency(IAEA). The regulatory frameworks of the Malaysia currently apply the Radiation protection(Transport) Regulations 1989, which adopts the IAEA’s Regulations for the Safe Transport ofRadioactive Material. The transport regulations apply to any activities involving transportation ofradioactive materials in Malaysia whether they transport by air, water-ways or inland (road andrailways). The regulation is also applied on any activities at economic exclusive zone. The Atomic
Energy Licensing Board (AELB) is the regulatory body who has the jurisdiction to enforce thetransport regulation.
In 1996, 2003 and 2005, the IAEA published revisions of their Regulations for the Safe
Transport of Radioactive Material and recommended that ‘adoption of these revised Regulations
occur within a period of five years from their publication to achieve worldwide harmonization of
their application. However, in Malaysia, since gazetted in 1989, the transport regulations neverbeen amended even though the IAEA’s regulation for the safe transport of radioactive material has
been amended. Nevertheless, the AELB has made initiative to amend the regulations and the newamended regulation is waiting to be read before the parliament.

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8. Mongolia
Part 1. Radiation Safety in Radioisotope Facilities ........................................................... 109
1.1 General ................................................................................................................. 109
1.1.1 Legal and Regulatory Infrastructure ...................................................................... 109
1.1.2 Emergency planning and response ........................................................................ 113
1.1.3 Control of orphan source...................................................................................... 113
1.1.4 Strengthening of export import control .................................................................. 113
1.1.5 Occupational exposure control........................................................................... 114
1.1.6 Public exposure control........................................................................................ 114
1.2 National Waste Management Policy and Strategy ..................................................... 115
1.2.1 Source of radioactive waste .................................................................................. 115
1.2.2 Long term storage facility for spent or disused sources ........................................... 116
1.2.3 Clearance Regime for Radioactive Waste .............................................................. 116
1.2.4 Storage of Radioactive Waste ............................................................................... 116
1.2.5 Disposal of Radioactive Waste.............................................................................. 116
1.2.6 Decommissioning of Nuclear and other Facilities Containing Radioactive Materials ...... 117
1.2.7 Remediation........................................................................................................ 117
1.3 Future goals and priorities ....................................................................................... 117

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8. Mongolia
Part 1. Radiation Safety in Radioisotope Facilities
1.1 General
Mongolia is a landlocked country inNorthern Asia between Russia and China and it
has a population of 2,73 million and an area of
1.5641 million square kilometres. It is ranked as
the seventh largest country in Asia and the 18thlargest in the world. With 1.72 people persquare kilometre, it is one of the least densely
populated countries in the world.
Mongolia became a Member State of the IAEA
in 1973 and is a member of FAO, ILO andWHO.
1.1.1 Legal and Regulatory Infrastructure
1.1.1.1 Mongolia's nuclear weapon - free status
Mongolia declared itself in 1992 a nuclear weapon - free zone. The United Nations General
Assembly adopted its Resolution on Mongolia's international security and nuclear weapon free status. A law on nuclear weapon free status enacted in Mongolia to institutionalize thisstatus.
1.1.1.2 International legal framework
Mongolia has been an IAEA Member State since 1973 and is a party of the following IAEA
Multilateral Agreementso Agreement on the Privileges and Immunities of the IAEA
o Convention on the Physical Protection of Nuclear Materialo Convention on Early Notification of a Nuclear Accident
o Convention on Assistance in the Case of a Nuclear Accident or Radiological
Emergencyo Revised Supplementary Agreement Concerning the Provision of Technical Assistanceby the IAEA (RSA)o Third Agreement to Extend the 1987 Regional Co-operative Agreement for Research,
Development and Training Related to Nuclear Science and Technology (RCA)o Application of safeguards in connection with the Treaty on Non-Proliferation of
Nuclear Weapons (with Protocol)
o Protocol Additional to the Agreement between Mongolia and the International Atomic
Energy Agency for the Application of Safeguards in Connection with the Treaty on the
Non-Proliferation of Nuclear Weapons
Currently Mongolia is considering to join the Convention on Nuclear Safety and Joint
Convention on the Safety of spent fuel management and on the safety of radioactive waste
management. Some of the necessary arrangements have been made.

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1.1.1.3 Nuclear Fuel Cycle Aspects
Currently, Mongolia has no power reactors or research reactors. It has no nuclear fuel cycle
facilities except for a uranium ore processing facility, located in northeast Mongolia that is on
standby.
1.1.1.4 Legislative Framework
The Parliament of Mongolia has passed the Nuclear Energy Law, which entered into force inAugust, 2009. The law on Radiation Protection and Safety has been repealed 15 August 2009.
Regulatory and both nuclear and radiation safety issues regulated by the Nuclear Energy Law.
Powers and activities of the Nuclear Energy Agency and its regulatory functions has been
described in Nuclear Energy Law.
Regulations and Guidanceo Radiation Safety Standard (1983)o Basic Regulation on Radiation Sanitation (1983),
o Transport Regulation for Radioactive Sources (1987).
o Draft of updated regulations for IAEA BSS conformity has been prepared.
o Mongolian National Standard. MNS 6240-2011. Technical Requirements for the
Packaging of Radioactive material /Updated by the IAEA Regulation, 1996/o Radiation Safety Regulation on Diagnostic Radiology, 2011
o Safety Regulation for the Use of Densito/Moisture Gauges in Road Construction. 2011o The dose limits in the Radiation Safety Standard (1983) have been updated by the
Mongolian National Standard MNS 5631:2006 and MNS 5630:2006.
NORM Regulations for Oil-Gas Industry has been developed by NEA and submitted to theGovernment for approval. Safety regulations for Uranium exploration And Processing is indeveloping stage.
Mongolia is encouraged to continue to participate in the Agency’s legislative assistanceactivities which aim to promote adherence to and implementation of international agreements,
guidelines and recommendations and to support Mongolia in its efforts to establish, develop, or
review its national laws and regulations governing the safe and peaceful uses of nuclear energy
and in adopting implementing legislation for the international instruments to which it has orintends to adhere.
1.1.1.5 Regulatory body and its functions
Mongolia participated in activities of IAEA interregional Model Project INT/9/143 from June
1996. Under this project Mongolia achieved good progress for establishment of independent
regulatory body and first law on Radiation Protection and Safety has been approved by the
Parliament. The Nuclear Regulatory Authority /NRA/ has been established by Governmental
Resolution No 180 dated 13 August 1997 under the Nuclear Energy Commission (NEC) of theGovernment of Mongolia as the Regulatory Body in Mongolia. It has restructured the under theState Specialized Inspection Agency /SSIA/ during 2003-2005 as the independent regulatory bodyfrom promotional activities, but status of NRA within the SSIA was not very effective andcompetent.

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Government of Mongolia established the Nuclear Energy Agency (NEA) under thecompetence of the Prime Minister to serve as the government regulatory agency in January, 2009by the Government Resolution No.64 (24 Dec 2008) “Establishing Regulatory and Implementing
Agency of the Government”.
According the Government decision, the Regulatory body (NRA) has been restructured into the
NEA as Nuclear and Radiation Regulatory Authority /NRRA/ since January, 2009 and separated
from SSIA.
Parliament Decision No.45 of 2009 adopted State Policy of Mongolia on the Exploitation ofRadioactive Minerals and Nuclear Energy.
The Governmental Regulatory Agency - Nuclear Energy Agency under the Prime Minister is
responsible for development of policy for the activities related to development of nuclear researchand technology, radiation protection and nuclear safety, use of radiation sources and coordinationof uranium mining activity with other relevant organizations.
NEA has following departments:o Department of Administrationo Department of Nuclear Technology
o Nuclear and Radiation Regulatory Authority (NRRA).

NNRA is responsible for implementation of regulatory functions of NEA described in Nuclear
Energy Law as regulatory body.
Authorization
Authorization system complies with international standards and the NRRA has implemented
an authorization program that covers all practices and applies a risk based approach toauthorization commensurate with the potential magnitude and nature of the hazard presented by
the practices, including separate requirements for registration and licensing.

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Inspection
The NRRA has established a planned and systematic inspection program. The inspection
frequency depends on the risks and results of previous inspection findings. There are planned,
announced and unplanned, unannounced and follow-up inspections carried out in accordancewith established procedure.
Enforcement
The authority for enforcement is specified in the Nuclear Energy Law and the Law ofMongolia on State Inspection. The Nuclear energy Law has a provision on responsibility to be
assumed by violator of nuclear energy legislation.
The enforcement policy has been established in the NEA procedure. This policy provides for arange of sanctions commensurate with the seriousness of the non-compliance. The NEA has alsoestablished formal arrangements with relevant government agencies where enforcement requires
the involvement of the police, justice ministry or other authorities.
The Nuclear Energy Law and the Law on Inspection empower inspectors to take on-the-spot
enforcement actions.
1.1.1.6 Inventory of Radiation Sources
The NRRA of NEA registers all identified sources, irrespective of whether they meet theexemption requirements. It has completed inventory of radiation sources and it has centralized
information database for all identified facilities and sources in the country. Regulatory nformation
including source and facility data used in RAIS and the hard copy versions in parallel. Smallcalibration sources also registred. The inventory has been updated using inspection findings andalso annual inventory reports from the users.
Radiation sources are used in the following fields:
 Medicine (radiotherapy, nuclear medicine and diagnostic radiology)
 Industry and mining
 Geology
 Science and Education
 Agriculture
Powerful sources are follows: Electron cyclic accelerator “Microtron MT-22” /20MeV Neutron generators (14 MeV) Californium-252 source Radiotherapy, /Cobalt-60 teletherapy unit/ Research irradiator with Co-60 sources
 Waste storage facility
Practices with security concern:
Category 1. Security level Ao Teletherapy (Co-60)
o Research irradiator (Co-60)
Category 2. Security level B
o Industrial gamma radiography (Ir-192)
o High/medium rate brachytherapy (Co-60)
Category 3. Security level Bo Well logging /borehole logging/ (Am/Be, Cs-137)

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o Industrial fixed gauges with high activity sources (Cs-137)
Category 4. Security level Co Low dose rate brachytherapyo Fill / Thickness gaugeso Portable gauges (e.g. moisture / density)
Category 5. Security level D
o XRF devices
1.1.2 Emergency planning and response
Nuclear and radiation emergency responses in Mongolia are coordinated by the National
Emergency Management Agency /NEMA/ where NEA plays a role within a multi-agency
response. The first responders from the NEMA have been trained abroad in radiation emergency
planning, preparedness and response. A general law requires users of radiation sources to contact
the NEA and the NEMA in the event of an emergency and an accident.
1.1.3 Control of orphan source
There was query as to what effort, if any, was made to determine if there were abandoned sources
due to the industrial economic disruptions, transition period from centralized to market economy
and government changes of the 1990’s. By closely working with potential users (survey through asystem of notification) of radiation sources, about 20 orphan sources are being identified andsecured during 1995-2008 with cooperation of authorized users and other relevant Agencies.
Orphan or abandoned radiation sources should be secured and stored at Isotope office without any
charge by the Law and regulations. Requirements on reporting loss of control and to encourageawareness of, and monitoring to detect, orphan sources has been described in the Nuclear Energy
Law.
1.1.4 Strengthening of export import control
Mongolia covers a vast territory and shares a long border with its two neighbors. For a country
with this geography and a small population, border management is becoming a serious challenge
at a time of increased concerns over transnational crimes, including trafficking in nuclear-related
items. Mongolia’s efforts to respond to the threat of nuclear smuggling have been beset by ashortage of trained personnel and necessary equipment.
Mongolia has decided to focus in the course of UNSCR 1540’s implementation first on
developing effective border controls to detect cross-border smuggling of nuclear-related items.
Under the MOU, the US Department of Energy is providing Mongolia technical assistance in theform of equipment, materials and training for use at border ports for the purpose of detecting andinterdicting illicit trafficking in special nuclear material and other radioactive material. The
deployment is being carried out under its Second Line of Defense Program.

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1.1.5 Occupational exposure control
Nuclear and Radiation Regulatory
Authority of the NEA provides:
 Occupational exposure control/external exposure only/ About 1213 radiation workers
from 163 organizations underregular personal dosimetry
control as of 20 November
2011 /98%/
Weaknesses:
 Internal dosimetry is notestablished Personal monitoring for radonand neutron are not available
Number of Radiation Workers (2003-2011)

1.1.6 Public exposure control
1.1.6.1 Environmental Monitoring
Environmental monitoring is carried out by the Radiation Laboratory of the NRRA of NEA
using the environmental monitoring network of the Ministry of Environment. Needs tostrengthening of environmental monitoring network for the ensuring of emergency preparedness
purposes.
Air fallout samples for gross beta measurement are collected in 23 local stations. Aerosol grossbeta activity measurement, on filter samples of typically 100-130 m3 of air daily in Ulaanbaatar
city. In addition, at 35 meteorological stations, ambient gamma dose rates are measured twice a
day with portable dose rate meters and transmitted to the meteorological centre in Ulaanbaatar
three times a month. NEA worked out a Project Proposal for Establishment of online
Environmental Radiation Monitoring Network submitted it in 2011 to the Government for
approval.
Due to the large scale nuclear weapons testing programmes in 1970, near Mongolia’s borders; theenvironmental monitoring program in these regions was focused to the analysis of air, water andsoil samples. There is an urgent need for more enhanced measurements for alpha and beta
contamination.
1.1.6.2 Control of Foodstuffs
A national system (logistics and/or technical capabilities) for monitoring the levels ofradioactivity in foodstuffs and selected commodities before they go for trading exists and controls
appear to have been established by the Regulatory Body.
More than 2150-2500 imported food samples per year are monitored in Mongolia. The foodsamples are initially screened with a food contamination monitor (Berthold LB200) measuring
gross gamma activity. Food samples showing unreasonably high gross gamma activity (comparedwith an investigation radiation level for different kinds of foodstuff) are carefully measured again
with a high-resolution gamma spectrometer with HPGe detector. There are 3572 and 2717
samples from domestic and imported foodstuffs have been monitored radionuclide contamination

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by Radiation Laboratory of NRRA of NEA in 2008 and 2009 respectively.
In addition to that, there is a daily monitor of tap water in Ulaanbaatar city, and regularmonitoring of water samples from 8 different regions.
1.1.6.3 Control of Chronic Exposures
As of 2010, Mongolia had 48 coal mines, 22 mines of other mineral resources and 87
building material factories under the regular sampling program by the regulatory body.
Radiation control for the non-uranium underground mines are not in place.
Regulatory control in NORM workplaces except uranium projects is not in place caused byshortage of manpower, resource, laboratory capabilities and it is not regulated by legislation.
Potential chronic exposure scenarios have been identified in the country but they are notcharacterised sufficiently. NORM generating industries have not been identified in the country
completely.
There is an urgent need for continuing indoor radon measurements due to the extensive use ofcoal ash as a building material. Radiation Laboratory provides limited service for determination ofradon content in water, soil, home and workplaces.
1.1.6.4 Control of Radioactivity in Materials For Recycling
In 2007, Mongolia had one iron manufacturing factory in Darkhan city which also processed
scrap metals. Portal monitors control the presence of significant amounts of radioactive substances
in materials going for recycling.
Scrap metal dealers do not have their own monitoring equipment. Scrap metal goes to China.
The recipient requires a Radiation Certificate for exporting scrap metals transported by rail andrequested that NRRA provide this. NRA measures the scrap metal with monitors when it is loaded
onto railcars.
Mongolia received assistance from Government of USA under the UN Security Council
Resolution 1540 and it was installed 73
Radiation Portal Monitors at the 12 main Portof Entry including entry/exit of rail, road and passenger. It is very useful for detection of orphan
sources in materials for recycling and screening of radioactivity in materials through the PoE.
1.2 National Waste Management Policy and Strategy
National radioactive waste management strategy is described in the on the Exploitation ofRadioactive Minerals and Nuclear Energy has been approved by the Parliament Decision No.45/2009/. Waste Management Program for Mongolia has drafted but not approved yet. Draft
regulations for waste management and safety currently being developed.
1.2.1 Source of radioactive waste
Mongolia uses the IAEA classification system for radioactive wastes. Radioactive waste exists
in solid and liquid forms. Liquid wastes, which generated from nuclear medicine hospitals, havevery short half-life. When the activity of liquid waste falls below the IAEA clearance level, it isdischarged into the sewerage system. Most radioactive wastes are in the form of solid sealed
sources.
The sources of radioactive wastes are:i) Research facilitiesii) Medicine, Industrial and Militaryiii) Decommissioning of contaminated installationsiv) Mining and Milling
At present, the generation of unsealed radioactive waste material is not considered to be a

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problem, but the situation could be change with the development of new phosphate, oil, gas anduranium industries.
1.2.2 Long term storage facility for spent or disused sources
The NEA has a dedicated secured and fenced-off long term storage facility for spent, disused ororphan sources about 20 km from Ulaanbaatar. Mongolia has no disposal facilities. NEA has
long-term plan to convert the storage facility into a disposal facility. This facility has a camera
surveillance system and under security guard for 24 hours a day.

An appropriate waste classification scheme has been established based on the IAEA waste
classification scheme. Safety provisions and criteria for all radioactive waste management
facilities and activities are not in compliance with established safety criteria. However, adequate
provisions are not in place for ensuring that all existing radioactive waste, including disused sealed
sources, is kept to a minimum, adequately processed, stored or disposed of under regulatory
control.
NORM workplaces is not identified and there is strong need to establish regulatory criteria for
uranium industry and other activities producing NORM residues in Mongolia
There are only small quantities of radioactive waste in Mongolia; therefore, processing is not
carried out on a regular basis. There is also no procedure in place for the characterization andsegregation of radioactive waste. No special regulations for waste management of uranium
industry and NORM workplaces but an appropriate international standards are applicable forsafety assessment and enforcement.
There is no procedure in place for processing radioactive waste in order to ensure that
acceptance requirements for disposal are fulfilled, as well as the requirements for handling,transport and storage of waste packages, taking into account interdependency in all steps.
1.2.3 Clearance Regime for Radioactive Waste
Limits and conditions for the removal of regulatory control over materials containing
radionuclides exist and are in agreement with international recommendations. They appear to be
enforced by the Regulatory Body.
Liquid waste, generated from nuclear medicine hospitals, has a very short half-life. When theactivity of liquid waste falls below the IAEA clearance level, it is discharged into the seweragesystem.
1.2.4 Storage of Radioactive Waste
The Isotope Centre of the NEA has a national long term waste storage facility in Mongolia.
The Isotope Centre is located about 20 km from Ulaanbaatar. NEA paid much attention andcarried out appropriate measures for upgrading of Physical Protection of Isotope Centre during
2008-2010.
Several Co-60 sources of disused irradiator are stored in the Institute of Physics andtechnology of Academy of Sciences. Radionuclides use in nuclear medicine andradioimmunoassay assays (I-131, Tc-99m and I-125) are decayed in storage.
The NRRA has access to equipment and facilities for the handling and temporary storage ofradioactive sources, including following recovery of orphan or vulnerable sources through theIsotope Centre of the NEA.
1.2.5 Disposal of Radioactive Waste
Currently, there is no waste management policy and strategy with respect to disposal in
Mongolia. Plans are underway to create a disposal facility within the Isotope Centre of the NEA.
Isotope Centre had a small burial area where contaminated material from a Sr-90 incident was116

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buried in 1993 and its brief report was sent to IAEA.
1.2.6 Decommissioning of Nuclear and other Facilities Containing Radioactive Materials
There is no national waste management policy and strategy, so that funding mechanisms fordecommissioning need to be addressed.
There are no plans for the shut-down and decommissioning of nuclear and other facilities. The
research irradiator from Institue of physics and technology needs to decommissioning.
Recently, the Nuclear Research Centre of the National University of Mongolia requested
assistance in decommissioning a neutron generator. The neutron generator, being out of use for 15
years, was made in the former USSR and was used for research and training.
1.2.7 Remediation
Mongolia carries out uranium ore remediation near the former Mardai Uranium Mine which islocated in the Dornod province and in the eastern part of Mongolia. The amount of the uranium
ore amounts to 157,000 tons and 35,000 tons.
The Radiation Laboratory of the NRRA performs environmental monitoring measurements inorder to assess the potential risk in the tailings pile of former uranium ore and former mines.
There is an on-going IAEA TC Project on Environmental Impact Assessment andRemediation of the Uranium Mining Legacy MON/9/005 (since 2005). The project is being
implemented by the Ministry of Environment and the NEA. The project was completed in 2010.
1.3 Future goals and priorities
o Strengthening of regulatory infrastructure and regulatory control of nuclear andradioactive materials;
o Harmonization and developing of legislation and regulations for different practices
o Implementation of an effective system for detecting and preventing illicit trafficking of
nuclear and radioactive material;o Strengthening of radiological emergency response and planning at national level;o Establishment of the State system of accounting and control of nuclear material (SSAC);o Upgrading of Environmental Monitoring capabilities and Radiation Protection Technicalserviceso Establishment of internal dosimetry control and nationwide radon survey
o Strengthening of radioactive waste storoge facility and establishment of disosal faciliyo Adequate physical protection for all nuclear and radioactive material and facilities, and thetransport of such materials;o Upgrade the emergency preparedness and response capability in the country117

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9. The Philippines
Part 1. Radiation Safety in Radioisotope Facilities ................................................... 119
1.1 General ................................................................................................................. 119
1.1.1 Legislative framework and policy for radiation safety............................................. 119
1.1.2 Structure and System (Regulatory organizations) ................................................... 119
1.2 Outline of Radiation Facilities and Radiation sources ................................................ 119
1.2.1 Number of specialists and Workers in related organizations .................................... 119
1.2.2 Number of radiation sources including generators .................................................. 120
1.2.3 Future plans and issues to be solved ...................................................................... 121
1.3 Education and Training........................................................................................... 121
1.3.1 Radioisotope usage .............................................................................................. 121
1.3.2 Radiological protection ........................................................................................ 122
Part 2. Radiation Safety in Research Reactors, NPPs and Other Various RI Usage ........... 122
2.1 Radiation Safety in various RI usage........................................................................ 122
2.2 Radiation Safety in Research Reactors ..................................................................... 124
2.2.1 Radiation Safety Management System .................................................................. 124
2.3 Radiation Safety in Radioactive Waste Management ................................................. 125
2.3.1 Radiation Safety Management System .................................................................. 126
2.4 Radiological Protection for Radiation Workers ......................................................... 128
2.5 Radiological Protection for Radiation Area............................................................... 128
2.6 Radiological Protection for the Public ...................................................................... 129
2.7 Radiation Emergency Preparedness ......................................................................... 129

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9. The Philippines
Part 1. Radiation Safety in Radioisotope Facilities
1.1 General
1.1.1 Legislative framework and policy for radiation safety
The Philippine legislative framework on radiation safety includes a hierarchy of laws,
executive orders and regulations under the National Constitution. The Science Act of 1958 (RA2067) created the Philippine Atomic Energy Commission (PAEC), the predecessor of the now
Philippine Nuclear Research Institute (PNRI), was mandated to promote the peaceful uses ofatomic energy and promulgate rules and regulations to ensure the safe use and application ofradioactive materials in the different fields of application. Ten years later, RA 5207 was enacted
to provide for the licensing and regulation of atomic energy facilities and materials.
In parallel, PD 480 (1974), as amended by PD 1372, EO 119 and EO 102 established theDepartment of Health (DOH) as the Regulatory Authority for the regulation of X-ray units andother electronically generated radiation devices, including non-ionizing radiation.
1.1.2 Structure and System (Regulatory organizations)
The regulatory framework considers nuclear facilities and radioactive materials separatelyfrom radiation emitting devices, with separate jurisdictions for each. The Philippine Nuclear
Research Institute (PNRI) through its Nuclear Regulations, Licensing and Safeguards Division(NRLSD) regulates the former, while the Department of Health (DOH) through its Bureau ofFood and Drugs’ Center for Device Regulation, Radiation Health and Research regulates the latter.
The PNRI has the roles of promoting nuclear technology, providing services, and regulating.
PNRI’s own nuclear and radiation activities, however are exempt from licensing as stated under
the current laws. To address this specific issue, PNRI has established an internal regulatory control
program which essentially delegated to the NRLSD of PNRI the authority and responsibility of
regulatory control over PNRI radiation facilities and research laboratories. An Office Ordersigned by the PNRI Director in 2004 clearly stated, among other things, that all PNRI radiation
facilities and laboratories must be authorized by the NRLSD at the end of 2006. A system ofauthorization is now in place for all of these facilities.
The DOH is responsible for the administration and funding of 72 DOH hospitals. The
Center for Device Regulation, Radiation Health and Research provides radiation protection
services in addition to regulating ionizing and non-ionizing radiation.
1.2 Outline of Radiation Facilities and Radiation sources
1.2.1 Number of specialists and Workers in related organizations
The number of specialists working in the two regulatory organizations accounts to less than500. The Philippines has 2 Secondary Standard Dosimetry Laboratories (SSDLs) under a
National SSDL Organization, a member of the IAEA-WHO SSDL Network, which are being
operated by the PNRI and the DOH, respectively. PNRI operates and maintains a SSDL fornational standard radiation dosimetry. It continues to provide a national monitoring service forexternal exposure to radiation to about 10,000 workers occupationally exposed to radiation using

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films and TLD.
Internal monitoring is not routinely conducted but in cases of probable
exposure, monitoring can be done by whole body counting or bioassay technique.
1.2.2 Number of radiation sources including generators
Table 1 gives the typical uses of radioisotopes in the Philippines while figure 1 displays thecategory of PNRI licensees based on types of use or application. Authorized practices and uses ofionizing radiation in the Philippines include the following.
Medical uses include: a gamma knife facility; a medical cyclotron/PET facility; a PET/CT
facility, 13 LINACs, 13 cobalt-60 teletherapy units, 7 HDR brachytherapy facilities, 3 blood
irradiators and 21 nuclear medicine facilities with SPECT capabilities; and 4,163 registereddiagnostic X-ray units.
Industrial uses include: a high energy electron beam machine and a Co-60 irradiator which
was upgraded with support from the IAEA TC project and from the US Department ofAgriculture; 113 industrial and anti-crime x-ray facilities; 38 industrial radiography licensees; andabout 650 sources used in industrial gauging applications.
Table 1: Typical uses of radioisotopes in the Philippines

USES
Hospitals

RADIOISOTOPES
I-131, I-125,Co-60, Ba-133, Sr-90, Cs-137, I-131, Tl-201,
Ga-67, Tc-99m, I-129, Ra-226, C-14

Industrial Radiography

Ir-192, Se-75, Co-60

Research and Education

Co-60, Cs-137, Sr-90, Ra-226, Th-232, Co-60, Cs-137,
Cs-137/Ba-133m

Industry(Fixedportable gauges)

and Sr-90, Kr-85, Po-210, Am-241, Cs-137, Am-241, Co-60, Cf-252,
Am-241:Be, Cd-109

Figure 1: Category of PNRI licensees based on types of use or application

The PNRI owns the country’s only research reactor, the PRR-1, which became critical in 1963.
The PRR-1 became the principal facility for many research and manpower activities in the field of120

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radioisotope production, neutron spectrometry, neutron activation analysis, and reactor physics.
By the early 1970’s routine production of some 30 radioisotopes and labeled compounds wasundertaken. The PRR-1 was converted into a TRIGA Facility designed for 3 MW operation in1984 and was expected to be operational in 1989. However, the PRR-1 has been shut down
since 1988 immediately after a successful critical testing when the reactor pool lining developed aleak. Philippine authorities have decided to decommission PRR-1 and have accepted to host the
IAEA Research Reactor Decommissioning Demonstration Project (R2D2P).
1.2.3 Future plans and issues to be solved
Radiation Control and Safety is continuously being updated and introduced by PNRI through,among others, its training program for all prospective users of radioactive materials in the country.
The modules usually include topics on radiation protection standards, dosimetry, personnel
monitoring, radiation control practices, emergency planning, radioactive waste management,
among others. Theoretical work is usually followed by experiments and case studies.
Standards and regulations are also continuously being updated to consider not only safety but
also security of radioactive sources. Current initiatives include the implementation of a Nuclear
Safety Caravan project to promote the open exchange of safety and security information among
the various stakeholders involved in the peaceful application of the atom. Effective
communication and exchange of information are important tools to achieve a sustainable highlevel of safety and security awareness for radiation facilities and related nuclear infrastructure in
the country. The PNRI strives for the public's proper understanding of nuclear technology andthe establishment of safety culture by providing opportunities for information exchange andaddressing the public's concerns and by using the collected efforts of all those involved to resolve
any public health issue.
1.3 Education and Training
1.3.1 Radioisotope usage
The Philippine Nuclear Research Institute (PNRI) provides different technical services to othergovernment agencies, private companies, medical institutions, the academe, and the generalpublic. One of these services is the provision of training courses in nuclear science and technology,
and nondestructive testing techniques (in cooperation with the Philippine Society for
Nondestructive Testing).
The training program of the PNRI on nuclear science and technology aims to familiarize
participants with the fundamentals of nuclear science and technology, the basic principles ofradiation protection, and the peaceful applications of nuclear technologies in agriculture, in
medicine, in industry, in esearch and the environment.
The nuclear training courses are offered every year to different groups such as medical
practitioners, science educators, researchers, engineers, and technicians.
The courses consist of lectures, experiments, film showings, demonstrations, workshops andcase studies. Examinations are given to assess the participants' understanding of the subject
matter being taught. Certificates of satisfactory completion are issued to participants who havedemonstrated satisfactory knowledge of the subject matter presented and the ability to apply it.
Some of these courses have been accredited by the Commission on Higher Education (CHED)
with masteral units.
Laboratories and facilities of the different research units in PNRI are made available to the121

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trainees. For certain training courses, PNRI makes arrangements with other private companies,
government agencies, universities, and hospitals for PNRI training participants to use theirfacilities.
The PNRI also provides its trainees with manuals containing lectures and laboratory
experiments written by Filipino scientists.
Participants in any course must be endorsed by the head of office if they belong to agovernment agency or a private company. Those participating on their own have to submit awritten request to join the course.
Nomination forms/application forms should be submitted together with the following:Transcript of academic records
Medical certification by nominee's Medical Officer as to his/her physical fitness toundergo training.

 Workshops/Seminars
Specialized subjects such as the safe transport of radioactive materials and emergency
planning and preparedness.
 Thesis Advisorship ProgramThis is open to any deserving and qualified graduate or undergraduate university/college
student who may wish to undertake the laboratory research portion of his/her thesis at the PNRI,
making use of PNRI facilities, equipment and instruments.
 Apprenticeship/On-the-Job Training
For students and technologists who would like to use nuclear techniques.
1.3.2 Radiological protection
Education and training in radiation safety and radiological protection is provided mainly by
the PNRI and the DOH’s Center for Device Regulation, Radiation Health and Research
regulates the latter. The training program of the PNRI on nuclear science and technology aims
to familiarize participants with the fundamentals of nuclear science and technology, the basic
principles of radiation protection, and the peaceful applications of nuclear technologies inagriculture, in medicine, in industry, in research and the environment.

Part 2. Radiation Safety in Research Reactors, NPPs
and Other Various RI Usage
2.1 Radiation Safety in various RI usage
Table 2 presents the various regulations currently issued by the Institute. The PNRI continue
to develop practice-specific Code of PNRI Regulations (CPRs) which are reviewed and revised
periodically through a system of consultations involving a number of stakeholders. The CPRs
are referenced and updated against the recommendations of the International Atomic Energy
Agency (IAEA), the International Commission on Radiation Protection (ICRP) and the various
codes of the USNRC, especially those referring to the licensing of the nuclear power plant.

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Table 2: Code of PNRI Regulations

CPR PART 2
CPR PART 3
CPR PART 4
CPR PART 5
CPR PART 6
CPR PART 7
CPR PART 8
CPR PART 9
CPR PART 10
CPR PART 11
CPR PART 12
CPR PART 13
CPR PART 14
CPR PART 15
CPR PART 16
CPR PART 17
CPR PART 18
CPR PART 19
CPR PART 20
CPR PART 21
CPR PART 20
CPR PART 21
CPR PART 23
CPR PART 26

Licensing of Radioactive Materials
Standards for Protection Against Radiation
Rules and Regulations on the Safe Transport of Radioactive
Materials in the Philippines
Reactor Site Criteria
Rule of Procedure for the Licensing of Atomic Energy Facilities
Licensing of Atomic Energy Facilities (under its original title“Regulations for the Licensing of Atomic Energy Facilities”)
Atomic Energy Facility Operator’s Licenses
Physical Protection of Nuclear Power Plants and Materials
Financial Security and Government Indemnity
Licenses for Industrial Radiography and Radiation Safety
Requirements for Radiographic Operations
Licenses for Medical Use of Sealed Radioactive Sources in
Teletherapy
Licenses for Medical Use of Radiopharmaceuticals
Licenses for Medical Use of Sealed Radioactive Sources inBrachytherapy
Licenses for Large Irradiators
Licenses for the Use of Sealed Sources Contained in Industrial
Devices
Licenses for Commercial Sale and Distribution of Radioactive
Materials
Licenses for Use of Radioactive Materials in Research and
Education
Licenses for Use of Radioactive Materials In-Vitro Clinical andLaboratory
Licenses to Manufacture and Dispense Radiopharmaceuticals
Licensing and Safety Requirements of Particle Accelerator
Facilities for the Production of Radioisotopes
Licenses to Manufacture and Dispense Radiopharmaceuticals
Licensing and Safety Requirements of Particle Accelerator
Facilities for the Production of Radioisotopes
Licensing Requirements for Land Disposal of Radioactive Waste
Security of Radioactive Sources

Currently, a number of these CPRs are being reviewed to ensure consistency with CPR PART3 which is largely based on IAEA SS 115, International Basic Safety Standards and the Code of
Conduct for the Safety and Security of Radioactive Sources including the additional guidance forthe export and import of radioactive sources. Appropriate security requirements in addition tosafety requirements are included for purposes of granting authorization for the use of radioactive
sources in the various fields of application. Priority is given to practices using Category 1, 2 and 3

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sources. Categorization of sources are practically based on the IAEA Categorization of Radiation
Sources which was published in 2000 and revised in 2003. In the interim period, these security
requirements are imposed as additional specific conditions of licenses subject to inspection andaudit for compliance monitoring.
Regulatory guidance documents, information packages and regulatory bulletins are issued topromote a common understanding of the regulations and to facilitate regulatory inspections andaudits for compliance monitoring purposes.
2.2 Radiation Safety in Research Reactors
Philippine authorities have decided to decommission PRR-1 and have accepted to host the
IAEA Research Reactor Decommissioning Demonstration Project (R2D2P). In 1999, all the 50
spent fuel elements were shipped back to the USA under a US program to recover all spentenriched uranium fuel of US origin. The only irradiated fuel elements that remained were thosefrom the TRIGA core.
At present, the Philippines has only the 115 slightly irradiated TRIGA fuel rods, plus 15 fresh
TRIGA and 2 MTR type fuel rods. The slightly irradiated fuel rods are stored in a wet stainlesssteel storage tank having a diameter of 12 ft. and a height of 16 ft. The fresh fuels are stored in
the dry gamma room. These fuels are all currently stored inside the shutdown research reactor.
After the proposed decommissioning of the PRR-1, a storage facility that meets the radiological,
safety and security requirements for special nuclear material is planned to be built near the PNRI
interim storage facilities for conditioned wastes. The fuel rods will be kept in storage until moredefinite plans are made for its use.
2.2.1 Radiation Safety Management System
The Philippines has only one research reactor (PRR-1) and is currently undergoing
decommissioning. The regulatory process for the decommissioning of PRR-1 and related
activities is defined by the PNRI Internal Regulatory Control Program, which is the internal
authorization process set up in 2004 through PNRI Office Order 002 series of 2004. The
Regulatory Safety and Security Board was instituted to coordinate the request for authorization on
the operator side and be the link between the NRLSD and the radiation facility operators. Nuclear
safety and radiological protection are a primordial pursuit, much as adherence to international
standards and criteria in the area of decommissioning and compliance with local regulatory
requirements, such as those embodied by the relevant Code of PNRI Regulations (CPRs).
With respect to local regulations, the decommissioning effort is committed to comply with thefollowing: CPR Part 2, on Licensing of Radioactive Material; CPR Part 3, on Standards forProtection Against Radiation; CPR Part 4, on Regulations for the Safe Transport of Radioactive
Materials in the Philippines; and CPR Part 26, on Security of Radioactive Sources. The
administrative limits applied to PRR-1, which are at levels lower than the regulatory limit onradiation exposure of workers, will also be adhered to.
The decommissioning of the PRR-1 will also comply with the IAEA safety standards. The
project receives technical assistance from the IAEA, and the IAEA requires such compliance as acondition for assistance. This requirement has been published in IAEA Information Circular 127,
The Revised Guiding Principles and General Operating Rules to Govern the Provision ofTechnical Assistance by the Agency, March 1979.

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The IAEA Safety Requirements that will notably be applied (among others) to PRR-1
Decommissioning are:a.

Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing
Radiation and for the Safety of Radiation Sources. February 1996. STI/PUB/996.
b. Safety Standards Series No. WS-R-2, Predisposal Management of Radioactive Waste,
Including Decommissioning. July 2000. STI/PUB/1089.
c. Safety Standards Series No. WS-R-5, Decommissioning of Facilities Using Radioactive
Material. October 2006. STI/PUB/1274.
The following IAEA Safety Guides, Safety Reports, and Technical Reports are notably being
used (among many others) to guide compliance with the IAEA Safety Requirements:
a.
b.
c.
d.
e.
f.
g.

Safety Standards Series No. RS-G-1.7, Application of the Concepts of Exclusion,
Exemption and Clearance. August 2004. STI/PUB/1202.
Safety Standards Series No. WS-G-2.1, Decommissioning of Nuclear Power Plants andResearch Reactors. October 1999. STI/PUB/1079.
Safety Standards Series No. WS-G-5.1, Release of Sites from Regulatory Control on
Termination of Practices. November 2006. STI/PUB/1244.
Safety Standards Series No. WS-G-6.1, Storage of Radioactive Waste. November 2006.
STI/PUB/1254.
Safety Reports Series No. 45, Standard Format and Content for Safety Related
Decommissioning Documents. July 2005. STI/PUB/1214.
Safety Reports Series No. 50, Decommissioning Strategies for Facilities Using Radioactive
Material. March 2007. STI/PUB/1281.
Technical Reports Series No. 389, Radiological Characterization of Shut Down Nuclear
Reactors for Decommissioning Purposes. October 1998. STI/DOC/010/389.

2.3 Radiation Safety in Radioactive Waste Management
Radioactive wastes in the Philippines are generated from the applications of radioactive
materials in medicine, industries and research. The Philippine Nuclear Research Institute (PNRI)
currently manages these wastes through its centralized treatment and storage facilities located onsite. Radioactive wastes that are received at the Institute are of different types ranging fromcontaminated solid and liquid materials to spent sealed sources, including radium. The
Philippines does not have an operating nuclear power plant hence the amount of radioactive wasteis small compared to countries with nuclear power program. The amount of presently stored
waste plus expected institutional waste is estimated at about 3000 m3. In addition, thecontaminated wastes from the Philippine Research Reactor which is expected to be
decommissioned soon will generate a considerable volume of waste that need to be considered.
The volume of the decommissioning waste will depend on the decommissioning technology thatwill be employed and the application of the clearance levels for bulk solid materials. The
institutional waste also includes a considerable amount of spent sealed sources used in medicine
and industry. More than 2400 sources representing a total activity of approximately 3.61014 Bq
are listed in the waste inventory. Historical waste with an unknown radionuclide spectrum andactivity is also present. The inventory of spent sealed sources currently in store at the PNRI
Radwaste Management Facility. On-going work is being done to undertake complete

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documentation of solid and liquid waste.
The Philippines issued in 2000 a regulatory policy on the use of radium sources for human use
following its participation in the IAEA Radium Conditioning Project. A Philippine team underadvisement of an IAEA Expert collected and successfully conditioned all the previously
authorized radium sources in March 2001.
Decommissioning of all disused Co-60 teletherapy sources in the country and the subsequent
management of these sources have been successfully undertaken and completed in 2004 with theassistance of the IAEA.
These conditioned sources are now safely stored at the PNRI interim storage facilities awaiting
final disposal. The PNRI continue to pursue the upgrading of its centralized facility for low tointermediate level radioactive waste treatment facility with assistance from the IAEA through the
INT project on sustainable development. Moreover, the PNRI in collaboration with othergovernment agencies is currently evaluating the possible implementation of the IAEA
recommended Borehole Disposal Concept for disused sources.
The government is currently pursuing a project on the final disposal of all radioactive waste
including disused sources. Site selection studies and preliminary assessment are on going. All
activities take into consideration not only the requirements of CPR Part 23 mentioned above but
also international best practices practicable in the selection, design and operation of a waste
repository, as appropriate.
2.3.1 Radiation Safety Management System
The Philippines has only one (1) operating centralized facility for radioactive waste treatment,
conditioning and interim storage of all radioactive waste generated in the country. The facility
has a total land area of about 0.4 hectare and a floor area of about 600 m2 located inside the PNRI
compound in Quezon City. The facility includes the following: wet laboratory for R&D
activities, shielded cell and decontamination rooms, compressive strength testing area for concrete
specimens, decay storage room, chemical precipitation area, cementation area for conditioning
process and compaction area for compactible wastes. The interim storage for conditioned wastes
has a total capacity of about 535 m3. It is a concrete-lined trench with concrete slabs roofing
and an opening on one end with access from the Radioactive Waste Management Facility(RWMF) Building. In addition, a decay storage room having a capacity of about 100m3 is alsopresent. The facility has a truck entrance leading to the basement level of the building. This
serves as the only entrance for large and heavy waste packages for management and also serve as
the emergency exit for personnel in case of any untoward incident.
This facility is subject to authorization in accordance with PNRI Policy Instruction No. 02
Series of 2001, “Radiological Health and Safety Policy” and PNRI Office Order No. 002 Series of2004 “Regulatory Control Program for PNRI Nuclear and Radiation Facilities and Laboratories.”
Regular inspections are also carried out to verify compliance to the authorization issued by the
PNRI regulatory division.
Two important regulations govern the safe management practices of radioactive waste in thePhilippines. These are :1) The Code of PNRI Regulations (CPR) PART 3 entitled Standards for Protection Against
Radiation is largely based on IAEA SS 115 International Basic Safety Standards provides
for the general requirements involving waste management and disposal of licensed

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radioactive material include (a) storage under controlled conditions, (b) control andmonitoring of environmental discharges, (c) regulatory limit for airborne and waterborne
discharges adopting the IAEA Clearance Levels for waste resulting from medical, industrial
and research application of radioactive materials and the IAEA Safety Guide No. RS-G-1.7
entitled “Application of the Concepts of Exclusion, Exemption and Clearance for solid wastematerials. In the case of disused sources, the licensee has the following options in the
management of disused sealed sources: (a) transfer of source to another licensee forapplication or use at the current activity level, (b) decay storage of short half life disused
sources, (c) return to the original manufacturer or supplier. These options should bethoroughly considered prior to disposal at the PNRI Centralized Radwaste Treatment andStorage Facility.
2) The CPR Part 23 entitled Licensing Requirements for Land Disposal of Radioactive Waste
contains technical and procedural provisions applicable to all phases of the lifecycle of a
LLW Facility. This includes specific technical requirements involving siting, design,operations and closure, monitoring, waste classification, and institutional requirements. The
requirements were basically based on international best practices and accepted guidelines
such as those recommended by the IAEA.
The PNRI adopts two basic waste treatment and conditioning options for radioactive waste.
These are (a) waste collection and packaging for decay storage for final disposal as ordinaryrefuse; (b) waste collection, segregation, treatment, conditioning and packaging, followed byinterim storage awaiting final disposal in a repository. The last option includes compaction, as
appropriate and chemical precipitation, ion exchange of aqueous wastes. Depending on
chemical composition and physical properties, wastes are appropriately treated and immobilized
in cement prior to interim storage. Conditioned wastes are then coded in accordance with asystem established for the purpose.
Two above ground roofed trenches with a maximum capacity of 315 m3 and 220 m3,
respectively serve as the interim storage for conditioned radioactive waste prior to final disposal.
The facility also includes a 100 m3 storage room for decay.
Criteria to define Waste Category
The Comprehensive Hazardous and Nuclear Waste Management Act that is currently undergoing
the legislative mill defines the criteria for radioactive wastes as follows:
1. Exempt Wastes (EW) are radioactive wastes with activity level at or below clearance levels set
by the PNRI which are based on an annual dose of 0.01 mSv to members of the public
2. Low and intermediate wastes (LILW) are radioactive waste with activity or concentration level
above the clearance levels set by the PNRI. LILW may be a short lived waste or a long lived
waste. A short lived waste (LILW-SL) is a waste containing radionuclide with half lives
below or equal to the limits set by the PNRI. Long lived wastes (LILW-LL) are wastes
containing radionuclides with long half-lives and with activity exceeding the short lived waste
limits set by the PNRI; and3. High level waste (HLW) is radioactive waste with activity or concentration level exceeding thelimits for low and intermediate waste set by the PNRI.

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2.4 Radiological Protection for Radiation Workers
PNRI regulations clearly define exposure limits involving sources of ionizing radiation to bothradiation workers and members of the public. These limits strictly adhere to the International
Basic Safety Standards (IBSS) recommendations. The regulations also prescribe the appropriate
corrective measures to be implemented to control the release of radioactive materials into theenvironment and mitigate its effects.
Licensed facilities are also required to submit radiation protection and safety program which
includes functions, responsibilities, and qualification and training of individuals.
The PNRI ensures that the following dose limits will not be exceeded by the radiation
workers.
a) An effective dose of 20 mSv per year averaged over five consecutive yearsb) An effective dose of 50 mSv in any single yearc) An equivalent dose to the extremities (hands and feet) or the skin of 500 mSv in a year
A national monitoring service for external exposure to radiation to about 10,000 workers
occupationally exposed to radiation using films and TLD is being provided by the PNRI.
The PNRI provides dosimetry laboratory services for the calibration and standardization ofradiation measurements in the country through its Secondary Standards Dosimetry Laboratory(SSDL). The SSDL was established in 1974 and is a member of the International Atomic Energy
Agency-World Health Organization (IAEA-WHO) network of SSDLs. Metrological controls andcertification of measuring equipment for ionizing radiation are conducted at the PNRI’s SSDL toensure compliance of radiation protection and dosimetry practices with international measurement
standards. Beneficiaries of the SSDL services are the different radiation facilities of PNRI and
PNRI-licensees in private and government institutions using radiation and radioactive materials in
medicine, industry, agriculture, research, and training.
The Radiation Protection Services Section of PNRI maintains the SSDL with its equipment
and source standards for the provision of services for the calibration of radiation monitoring
instruments and dosimeters (i.e. survey meters, pendosimeter, rate meter, personal monitors;
output calibration of brachytherapy, teletherapy and activity meters in hospitals; and radiation
monitoring and hazards evaluation of radiation facilities.
Efforts to strengthen the capability for providing dosimetry and calibration services are beingexerted to have a wider range and more practice-specific technical service thus ensure theaccuracy and control of occupational and medical radiation exposures in the country. Some of
the areas that are to be pursued and improved include: beam quality measurements andcharacterization of the x-ray generator; establishment of protection level radiation dosimetry
standards using x-ray, Co-60 and Cs-137 radiation qualities; calibration for dose and energy
response of personnel and area monitoring instruments for gamma ray and x-ray standards in thelow, medium and high energy range; standardization and calibration of quality assurance
measurement tools for medical, x-ray, radiotherapy and nuclear medicine applications; anddevelopment of neutron and beta dosimetry protocols.
2.5 Radiological Protection for Radiation Area
As part of the regulatory requirements of PNRI, all licensed stakeholders are required toperform monitoring of their workplace from radioactive contamination. The PNRI conducts
regulatory inspections annually and verifies that the work areas are free from contamination.

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The licensees can also request technical services from the PNRI to ensure safety in theirfacilities. Among the services provided by the institute are the following.
i.
Leak testing of sealed radiation sources
ii. Radiation hazards evaluation of radiation faciltiesiii. Collection and management of disused radioactive sources, solid and liquid radioactive
wastes.
These services are provided b y the Radiation Protection Section of the PNRI for a specific fee.
The schedule of fees for the different services of PNRI has been published for ease of reference ofthe stakeholders.
2.6 Radiological Protection for the Public
Public and environmental safety is implicitly stated as a matter of government policy for all
projects or undertakings. This is emphasized in the specific provisions in the Codes of PNRI
Regulations which the Institute follows in its licensing process. Dose limits to the public follows
the recommendations stated in the International Basic Safety Standards.
Each licensee shallensure that the estimated average dose to any member of the public does not exceed the following
dose limits:(a) An effective dose of 1 mSv in a year;(b) In special circumstances, an effective dose of up to 5 mSv in a single year provided that the
average dose over five consecutive years does not exceed 1 mSv per year;(c) An equivalent dose to the lens of the eye of 15 mSv in a year; and(d) Equivalent dose to the skin of 50 mSv in a year
The PNRI’s Health Physics Section has been actively involved in the management of aninternational monitoring system to verify compliance to the Comprehensive Nuclear Test Ban
Treaty which was ratified by the Philippine Senate in 2001. The radionuclide monitoring
station (RN52) which is co-located at our National Weather Bureau station is now part of the 321
global network of the International Monitoring System (IMS) that collect data on evidence of
nuclear tests.
Several nuclear research projects that seek to protect environmental and public safety are also
being implemented by PNRI. These projects include the following.
1. Access to Clean Drinking Water
2. Control of Harmful Algal Bloom
3. Air Pollution Characterization
4. Radiological Impact of TENORM
5. Environmental Radioactivity Surveillance
In addition, the PNRI also provides services, upon requests, on the certification ofradioactivity content of foodstuffs for export and monitoring and clearance of scrap metals forexport.
2.7 Radiation Emergency Preparedness
Emergency Planning and Preparedness is part of the licensing process. All licensees
including PNRI authorized facilities are required to prepare and submit a facility emergency
response plan for approval of the regulatory body. The level of preparedness is commensurate to
the level of hazards expected in the facility.

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The PNRI in collaboration with 16 government agencies developed and maintains the
National Radiological Emergency Response Plan (RADPLAN) which covers any peacetime
radiological emergency that has or is expected to have a significant radiological effect within thePhilippines, and its territorial waters and which requires a response by several governmentorganizations. There are five major types of radiological emergencies that are covered by thisRADPLAN. These are:a) Emergencies from fixed nuclear or radiation facilities.
An emergency of this type is one that occurs at a facility with licensed or regulated radioactive
sources in their installations. Included in this category are the following:- Nuclear Facilities owned and operated by the PNRI
- Nuclear Reactors- Industrial or Medical Facilities licensed to use, possess, or import radioactive
materials or equipment containing radioactive materials- All other facilities or establishments using or possessing radioactive
materials.
b) Emergencies Occurring in the Transport of radioactive materials.
An emergency of this type is one that involves radioactive materials or wastes beingtransported by land, sea, or air inside Philippine territories. This includes the hazards from lost,missing or stolen radiation sourcesc) Emergencies from foreign sources having environmental impact on Philippine territories.
This type of emergency is one in which radiation from a foreign source poses an actual,potential, or perceived threat to any area within the territorial limits of the Philippines. The
source may be an accident from a foreign nuclear power reactor (for example, Chernobyl),
radioactive waste repositories, fuel reprocessing plants, or from the testing of nuclear weapons.
This includes the possible entry of contaminated food, plants and other commodities from
affected areas outside the countryd) Emergencies from Satellites with Nuclear Materials as component
This is a special type of emergency in which a spacecraft with nuclear materials would land
within the territory of the Philippines.
e) Emergencies from Nuclear Ships.
This type of emergency is one that involves radioactive material or wastes from nuclear
powered seacraft including nuclear submarines.
The level of the government response to a specific emergency will depend on the type and theamount of radioactive material involved, the location of the emergency, the potential for impact
on the public and the size of the affected area.
The RADPLAN is currently being reviewed to integrate security of radioactive sources.

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10. Thailand
Part 1. Radiation Safety in Radioisotope Facilities ................................................... 132
1.1 General ................................................................................................................. 132
1.1.1 Legislation and regulations................................................................................... 132
1.1.2 Structure and System (Regulatory organizations) ................................................... 133
1.2 Outline of Radiation Facilities and Radiation sources ................................................ 134
1.3 Education and Training........................................................................................... 136
Part 2. Status of Radiation Safety Management ........................................................ 137
2.1 Radiation Safety in various RI usage........................................................................ 137
2.1.1 Inspection Program.............................................................................................. 137
2.1.2 Dose Limit of Radiation Workers.......................................................................... 138
2.1.3 Radiological Protection for the RI User ................................................................. 139
2.1.4 Radiological Protection for the Public ................................................................... 139
2.1.5 Radiation Emergency Preparedness ...................................................................... 139
2.2 Radiation Safety Management in Thai Research Reactor-1 ........................................ 140
2.3 Radiation Safety in Radioactive Waste Management ................................................. 142
2.3.1 Related law and regulation on RS&RWM ............................................................. 142
2.3.2 Safety assessment of Thailand Radioactive Waste Management Facility. ................. 143
2.3.3 Assessment Endpoints.......................................................................................... 145
2.3.4 Safety Management of Disused Sealed Source....................................................... 145
2.3.5 Radiological Protection for Radiation Workers....................................................... 145

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10. Thailand
Part 1. Radiation Safety in Radioisotope Facilities
1.1 General
Thailand set up the first nuclear institution “Office of Atomic Energy for Peace” (OAEP) in 1961,
following the enactment of the Atomic Energy for Peace Act (B.E.2504). Then, the Thai research
reactor went to criticality in October 1962. Thus the first step was taken in research and development
and towards as a better standard of living.
Recently, the Office of Atomic Energy for Peace (OAEP) was renamed to be Office of Atoms for
Peace (OAP), plays as the regulatory body arm to control the use of radiation and nuclear applicationsin Thailand by the authorization from Thai Atomic Energy Commission (Thai AEC).
At present, there are about 20,000 licenses including X-ray and radiation source possessions andutilizations in the country. These licensees are a heterogeneous mixture of individual andgovernmental institutions which possess the radionuclides of activity ranging from a few kilo
becquerel up to some gega becquerel. The type of nuclear facility, radiation facilities and radionuclide
utilizing facilities is vary on the development of the atomic energy techniques and application. At
present, Thailand has no nuclear power plant, but the feasibility study on Nuclear Power Plant
preparation was conducted by the Ministry of Energy and Electricity Generation Authority ofThailand (EGAT).
1.1.1 Legislation and regulations
The main laws and regulations regarding control of radiation sources and Atomic Energy are
as follows: Atomic Energy for Peace Act B.E.2504 (1961) and B.E.2508 (1965)
 MOST Ministerial Regulations B.E. 2550 (2007) on the Condition and Procedure ofLicensing Process on Radioactive Materials, Nuclear Materials, and Atomic Energy.
MOST Ministerial Regulations (2007) is as the requirements for the licensing processof the possession and utilization of radioactive materials, nuclear materials, and atomic
energy from radiation generators and from nuclear reactor. This regulation covers in board
areas. The main issues are the basic requirements for those licensee to prepare their
documents as well as their general radiation safety procedure for their workers andalso for the public; such as the radiation protection training to radiation workers,
radioactive waste management, dose limits, decommissioning, and etc.
 MOST Ministerial Regulation B.E. 2546 (2003) on Rules and Procedures of Radioactive
Waste Management. This regulation is as guidance for the radioactive material users tomanage their radioactive wastes. The main issues are for preparation of radioactive
waste before transport to the centralized RWM in the country ( it was the OAP ). However,since Dec 2006, the centralized RWM has been conducted by Radioactive Waste
Management Center (RWMC), Thailand Institute of Nuclear Technology (TINT). This
regulation included the recommendation to manage disused sealed radioactive sources,
which written that DSRS should be returned back to their original manufacturers. The
regulation also covers several important issues, such as waste classification, clearance132

FNCA Consolidated Report on Radiation Safety (Thailand)level of solid, liquid, gaseous waste. However, this regulation need to be revised for the
up-date conditions in the present time as well as the development of international standard
in several issues. The relative legislative framework for radiation safety is also provided
through Hazardous Substance Act (1992)
 Enhancement and Conservation of National Environment Quality Act (1992)
Note: The both Acts (1992) do not make specific provisions for radiation safety except
listing a radioactive material as one of a list of hazardous substances.
1.1.2 Structure and System (Regulatory organizations)Regarding to the Atomic Energy for Peace Act (1961), the Thai Atomic Energy Commission(AEC) plays as a National Regulatory Body. The OAP Secretary General is as the secretariat of theThai AEC. The Office of Atoms for Peace(OAP), Ministry of Science Technology plays as aregulatory functional arm of Thai AEC. There are several sub-committees appointed fromexternal experts and OAP staff to review all matters related to the regulatory function. The OAP
has authorized from the Thai AEC to regulate, control as well as pre-review the license of the
production, possession, and utilization of radioactive materials, research reactor, including
radiation generators, such as X-ray machines, then submit to the sub-committee and the Thai AEC
for further permits.
Since 1961, the OAP has had the roles of promoting nuclear technology, providing services,and regulating. Up to now, the OAP owns a nuclear research reactor and several radiation
facilities, however, all are exempt from licensing as stated under the current regulations. To
address this specific issue, the new Atomic Energy Act should be established. The regulatory
control program need to be improved. Therefore, R&D tasks on nuclear applications and related
nuclear service activities has been separated, and to be carried on by the Thailand Institute of
Nuclear Technology (TINT), as an implementer of nuclear research activities.
Thai Atomic Energy Commission
Ministry of Science and Technology(MOST)

14 Sub-committeesOffice of Atoms for Peace(OAP)
Bureau of Radiation Safety RegulationBureau of Nuclear Safety Regulation
Bureau of Regulation Supporting
Non-regulatory groups

Medical Application
Agricultural
Application
Industrial Application
LicensingofRadioisotopes
andNuclear Materials
Food
Processing
Technology
Reactor Safety
Etc.

Fig. 1: Nuclear Regulatory Organizations in Thailand

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1.2 Outline of Radiation Facilities and Radiation sources
Table 1: Type of Radiation Facilities in Thailand

Facilities

Number of Facilities/unit

Research Reactor

1

Isotopes Production

2

Synchrotron

1

Research Gamma Irradiator

5

Industrial Gamma Irradiator

5

Gamma Tele-therapy

25 facilities, 44 units

X-ray devices- Diagnosis and Therapy in medicine

About 8500

X-ray devices - Industry

About 1500

Linear accelerator (LINAC)

45

Medical Remote after-loader and Brachytherapy

56 units, 25 facilities

Level/density thickness or conveyor gauge

350

Industrial Radiography

23

Education andradionuclides

R&D

Laboratories

using

~250

PET cyclotron

3

Electron beam ( education)

1

Electron beam ( Jams-Irradiator)

1

Neutron Generator

1

Radioactive Waste Processing and Storage

1 center

Utilization in each category
 Radio-isotopes
Radio-isotopes of activity ranging from a few kilo becquerel up to some gega Becquerel
are possessed in many areas of applications. There are several radionuclides produced in the
country by Radio-Isotope Production Center, Thailand Institute of Nuclear Technology(TINT), such as I-131, P-32 and Tc-99 m.
Several radionuclides are used in R&D, medicine, and industry, such as Am-241, C-14,
H-3, I-125, I-131, Cs-134, Cs-137, Co-60, Sr-90, Kr-85, and etc.
 Accelerators
There are several accelerators in uses for educational organizations and research

134

FNCA Consolidated Report on Radiation Safety (Thailand)Institutes, such as synchrotron, neutron generator, and electron beam.
For the hospitals and clinic, linear accelerators (LINAC) and PET cyclotron are used
for therapy.
 Distribution of radioisotopes
Table2: Distribution of radionuclide use by its applications.
Category
application

byMedicalRadionuclide
Ga-67,Cr-51,Tc-99m,
Co-60,I-125,

Percent (%)

Remarks

13

SRS and RI30

SRS and RI

I-131,Tl-201,
H-3,C-14,P-32,
S-35,Ra-226, Sr-90
Education

P-32,S-35,Cr-51,Ca-45,

and ResearchTc-99m,I-131,Co-60,
Sr-90,Cs-137,
Am-241, Be

Industrial

Fe-55,Kr-85,Sr-90,
Cd-109,Cs-137,Co-60,
Ir-192,Am-241,
Am-241/Be, H-3

40

SRS

Am-241
Ra-226(lightning
preventer)

17

SRS

Others/consumer
products

Table 3.Number of Radioactive Source Users and Radiation Users (OAP, Nov2010)

Radioactive Sources User (Licensee)
Medicine
Industry
Research & Education
Others (smoke detector, lightning preventer)

129
377
280
160

Radiation User Licensee
Medical X-ray devices
Industrial and Security X-ray devices

8500
1500

Medical Electron accelerators (LINAC)
Custom Electron accelerators

35
10

PET cyclotron(medical)
Synchrotron (R&D)
Neutron Generator (education)

3
1
1

Electron beam (education)

1

Electron beam (industrial irradiator)

1

Nuclear research reactor

1

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1.3 Education and Training
The OAP and the TINT have experiences to arrange the national training courses related to theradiation protection for radiation users, and another safety aspects, such as safe managing ofradioactive waste, emergency preparedness and etc, as follows:-

Training Course on Radiation Protection for General Radiation Workers.
Training Course on Radiation Protection for Radiation Supervisors.
Training Course on Radiation Protection for Radiation Workers in Medicine.
Training Course on Radiation Protection for Radiation Workers in Industry
Training Course on Emergency Preparedness
Training Course on Radioactive Waste Management for Medical and R&D workers.
Training Course on Radioactive Waste Management for Industrial workers.
Refreshment Course on Radiation Protection for TINT staff (every 2 years)

TINT- In House Radiation Protection Training
The radiation protection training is conducted by the Technology Transfer Section which
cooperated with Nuclear and Radiation Safety Section. It is structured at different levels in order
to meet the needs of different categories of facility staff and researchers using radioactive
materials and the operators of research reactor. All personnel and visitors entering the TRR-1/M1
facility receive training in radiation protection sufficient for the work/visit, or shall be escorted byan individual who has received such training. The levels of training are as follows: Initial Training – All personnel permitted unescorted access in the TRR-1/M1 facility shallreceive training in radiation protection as required by the Ministerial Regulation. Initialtraining shall cover the following areas in sufficient depth for the work being done:a) Storage, transfer, and use of radiation and/or radioactive material in portions of therestricted area, including radioactive waste management and disposal.
b) Health protection problems and health risks (including prenatal risks) associatedwith exposure to radiation and/or radioactive materials.
c) Precautions and procedures to minimize radiation exposure (ALARA).
d) Purposes and functions of protective devices.
e) Applicable regulations and license requirements for the protection of personnel
from exposure to radiation and/or radioactive materials.
f) Responsibility exposure to radiation or radioactive materials.
g) Appropriate response to warnings in the event of an unusual occurrence ormalfunction that involves radiation or radioactive materials.
h) Radiation exposure reports which workers will receive or may request.
 Specialized Training – Certain personnel (e.g., reactor operators) require more in-depth
training than that described above. Such individuals shall successfully complete training over136

FNCA Consolidated Report on Radiation Safety (Thailand)

the following outlined topics in sufficient depth for the work being done and pass a written
examination with a minimum grade of 70%.
a) Principles of atomic Structureb) Radiation Characteristicsc) Sources of Radiationd) Interaction of Radiation with Mattere) Radiation Measurementsf) Biological Effects of Radiationg) Radiation Detectionh) Radiation Detection Practicesi) ALARAj) Radioactive Waste Management and Disposal
 Annual Refresher Training – All personnel permitted unescorted access in the TRR-1/M1
facility shall receive annual radiation safety refresher training. The annual training shall cover
the following areas in sufficient depth for the work being done:a) Review of proper radiation safety practices, including radioactive waste
management and disposalb) Occurrences at TRR-1/M1 facility over the past yearc) ALARA summaryd) Notable changes in procedures, equipment, facility, etc.
e)Part 2. Status of Radiation Safety Management
2.1 Radiation Safety in various RI usage
Radiation Safety Management in various RI usage, is regulated in accordance with the Atomic
Energy for Peace Act B.E.2504 and Ministerial Regulation B.E. 2550. The main issues arecomprised of the licensing system and requirements of radiation safety and security.
 The Act B.E.2504 (1961) is the main law governing radiation safety in Thailand. It is
stated in section 12 that all radiation sources have been subjected to licensing: OAP Orders B.E.2552 (2009) on the Forms for licensing of radioactive materials, nuclear
materials, and the use of atomic energy from radiation generators and the use of atomic
energy from nuclear reactor.
There are 4 types of License
 License for production, possession or utilization of radioactive materials
 License for utilize Atomic energy from radiation generator and from nuclear rector
 License for modification of source materials from the natural chemical form
 License for export and import of special nuclear material, by-product materials or source
materials
2.1.1 Inspection Program
The OAP has established a planned program for inspections of radioactive sources. How
frequency and extent of inspection depend on:

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FNCA Consolidated Report on Radiation Safety (Thailand) potential magnitude and nature of the hazard presented as determined by Thai radioactive

source categorization system the categorization system is used to set the duration of the licence which corresponds withthe categorization number
Table 4. Radioactive Source Categorization System.

Category
1

2

3

4

5

Source and practiceRadioisotope thermoelectric generators
Irradiators
Teletheraphy
Fixed multi-beam teletherapy (gamma knife)
Industrial gamma radiography
Nuclear Medicine (except Radioimmuno Assay)
High/medium dose rate brachytherapy
Fixed industrial gauges(level gauges, density gauges,
Well logging gauges
Portable gauges (moisture/density gauges)
Low dose rate brachytherapy
Thickness/fill-level gauges
Sealed source for research , activity > 400 MBq
Unsealed source for research, activity > 40 MBq
Low dose rate brachytherapy eye plaques and permanentsources
Analytical Device
Static eliminators
Bone densitometers
Sealed source ,40 MBq< activity <400 MBq
Unsealed source, activity < 40 MBq
Lightening preventer, smoke detector
Standard sealed source, activity < 40 MBq

Duration ofLicense/Inspection

1year/annually

2years/ every 2 years

3years/ every 3 years

3years/ every 3 years

3years/ every 3 years

Radiation licensee are required to submit radiation protection and safety program which
includes functions, responsibilities, and qualification and training of individuals.
2.1.2 Dose Limit of Radiation Workersa) An effective dose of 20 mSv per year averaged over five consecutive yearsb) An effective dose of 50 mSv in any single yearc) An equivalent dose to the extremities (hands and feet) or the skin of 500 mSv in a year
In addition, the safety culture was introduced to radiation users. They are enforced to follow
the radiation safety requirements and code of conducts which are mainly based on IAEA SS 115,International Basic Safety Standards and the Code of Conduct for the Safety and Security ofRadioactive Sources.

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2.1.3 Radiological Protection for the RI User
2.1.3.1 Dose Monitoring
The occupational radiation monitoring service for external exposure to about 25,000
workers using films, TLD and OSL has provided by Department of Medical Science, Ministryof Health which has the accreditation following ISO-17025.
The Department of Medical Science has provided dosimetry laboratory services for radiation
workers in the country through its Secondary Standards Dosimetry Laboratory (SSDL) since 1971.
The Department of Medical Science’s dosimetry laboratory is a member of the International
Atomic Energy Agency and World Health Organization Cooperation network in South-EastAsia.
The OAP-dosimetry laboratory has carried on Metrological controls and certification of
measuring equipment for ionizing radiation. The Bureau of Regulation Supporting maintains the
SSDL with its equipment and source standards for the provision of services for the calibration ofradiation monitoring instruments and dosimeters (i.e. survey meters, rate meter, personalmonitors, etc.)
2.1.3.2 Radiation Safety Service
The users can also request technical services from the TINT to ensure safety in their facilities.
Among the services provided by the institute are the followings:(i)
Leak testing of sealed radiation sources/ Contamination checking(ii) Certify of the Packaging of Sealed Radioactive Source.
(iii) Survey Meter(iv) Collection and management of disused radioactive sources, solid and liquid radioactive
wastes(v) Transportation of radioactive wastes and disused radioactive sources.
These services are provided by the TINT for service charges. The schedule of service-charge
for the different services of TINT has been published for ease of reference of the stakeholders.
2.1.4 Radiological Protection for the Public
Dose limits to the public follows the recommendations stated in the OAP- regulation based on
International Basic Safety Standards. Each licensee shall ensure that the estimated average dose to
any member of the public does not exceed the following dose limits:(i) An effective dose of 1 mSv in a year;(ii) In special circumstances, an effective dose of up to 5 mSv in a single year provided thatthe average dose over five consecutive years does not exceed 1 mSv per year;(iii) An equivalent dose to the lens of the eye of 15 mSv in a year; and(iv) Equivalent dose to the skin of 50 mSv in a year
Note : In addition, the TINT provides services, upon requests, on the certification of radioactivity
content of foodstuffs for export.
2.1.5 Radiation Emergency Preparedness
Emergency Planning and Preparedness is part of the licensing process. All licensees
including OAP authorized facilities are required to prepare and submit a facility emergency
response plan for approval of the regulatory body. The level of preparedness is commensurate to139

FNCA Consolidated Report on Radiation Safety (Thailand)

the level of hazards expected in the facility.
2.2 Radiation Safety Management in Thai Research Reactor-1 / Modification1 (TRR-1/M1)
TRR-1/M1 Safety Management System, regulated in accordance with the Atomic Energy for
Peace Act B.E.2504 and Ministerial Regulation B.E. 2550, is comprised of the Radiation
Protection program, the Radiation Monitoring program, the ALARA program and Access control.
The system was established by the Reactor Operation Section and the Safety Unit, which aresupervised by the TINT Executive Director. The Safety Unit is an administrative organization
for radiation protection management, which is performed by health physicists.
The goal of the Radiation Protection program of TRR-1/M1 is to allow the maximum
beneficial use of radiation sources with minimum radiation exposure to personnel. Requirements
and procedures set forth in this program are designed to meet the fundamental principles ofradiation protection, which are Justification, Optimization and Limitation. The legal dose limit for
both occupationally exposed personnel and the general public are 20 mSv and 1 mSv, respectively.
The Radiation Monitoring program was established to ensure that all radiation sources aredetected and assessed in a timely manner. To achieve this, the monitoring program is organized sothat two major types of radiation surveys are carried out; referring as routine radiation level andcontamination level surveys of specific areas and activities within the facility, and special radiation
surveys necessary to support non-routine facility operations such as shutdown periods.
The Gas tight area of the reactor is classified as a Controlled area and is equipped with apermanent monitoring system for both Gamma and Neutron (so-called RAM-Radiation Area
Monitoring). Effluent and airborne radiation monitors are located in the Gas tight area and theVentilation system. The monitoring systems are continuously measuring radioactive dust/particle
and volatile gas during reactor operation. The data is recorded with electronic devices and istransferred to the monitor and data storage system in the control room. The air pressure in Gas
tight area is negative pressure to ensure the radioactive materials are kept inside the Gas tightarea during reactor operation.
The water in the primary coolant system is sampled once a week and measured for fission
products by HP-Ge detector gamma spectrometer. Radioactive particle/gas and dust are also
sampled with an activated charcoal air filter. Hand and Shoe monitoring, including a portablecontamination survey meter are located in the Reactor hall entry and near the emergency door exit.
A decontamination facility shower- room is also located at the Reactor hall entry.
Radiation surveys inside and outside the controlled area are routinely performed by healthphysicists as per health physics procedures. Sample irradiation procedures and forms require
checks of radiation level each time a sample is removed from an irradiation facility by a healthphysicist. Experiment reviews and approvals require radiation surveys for new experiments andmodifications of ongoing experiments.
Radiation workers are required to wear protective clothing when they enter the Gas tight area.
Protective clothing, shoes and shoe covers are provided for all individuals who enter the gas tightarea, including visitors, to avoid contamination. Everyone is checked for contamination upon
exiting. Radiation workers must also wear at least one type of personal dosimeters. TLD’s areissued to each radiation worker every 3 months. Digital dosimeters-direct reading personal
dosimeters are provided for both radiation workers and visitors. Visitors must be escorted by an
Operator. The number of visitors at one time must not be greater than 20 persons.
The ALARA program is based on the guidelines found in Basic Safety Standards for Radiation

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FNCA Consolidated Report on Radiation Safety (Thailand)Protection. It incorporates a review of all TRR-1/M1 operations with an emphasis on operational
procedures and practices that might reduce TRR-1/M1 staff and operators exposure to radiationand lower potential radioactive effluent releases to unrestricted areas. Personnel radiation doses at
the TRR-1/M1 are minimized by considering use of the following ALARA actions when
performing work with radiation or radioactive materials.
 Reviewing records of similar work previously performed
 Eliminating unnecessary work Preparing written procedures
 Using special tools
 Installing temporary shielding Performing as much work as possible outside of radiation areas Performing mockup training Conducting pre-work briefings and post-work critiques Keeping unnecessary personnel out of areas where radiation exposure may occur
In addition to the above actions, the TRR-1/M1 ALARA program also contains the following
elements which are designed to enhance the effectiveness of the overall program: Exposure investigations are conducted when an individual receives greater than 1
mSv in one month or 3 mSv in one quarter. The investigation is focused ondetermining the cause of the exposure so that appropriate ALARA actions, if any,
can be applied.
 ALARA dose trend analysis charts are prepared quarterly and posted for review by
all TRR-1/M1 personnel.
 An annual inspection of the TRR-1/M1 ALARA program is conducted by anindividual who has no operational responsibilities at the TRR-1/M1. This
individual is appointed by the RSC and inspection findings are presented to the
RSC within 30 days after completion of the inspection.
 A health physicist is required to be involved during planning, design approval, andconstruction of new TRR-1/M1 instruments and facilities; during planning andimplementation of TRR-1/M1 reactor use; during maintenance activities; andduring management and disposal of radioactive waste. In addition, written
procedures are required to be reviewed by Health Physics Supervisor.
The procedures for radiation protection are written by Safety Unit in accordance with therelevant Quality Assurance program of the Institute, which is ISO9001 certified. All theprocedures are approved by the TINT Executive Director and reviewed by the Radiation Safety
Committee. The procedures include the policy, methods and frequencies for conducting radiation
surveys and air sampling; effluent monitoring; administrative measures for controlling access toradiation area; control of contamination of personnel and equipment; control of radioactive
materials transportation within facility; methods of handling and storage of sources, radioisotopes
and other radioactive material.
Radiation protection training is conducted by the TINT Technology Transfer Section which
cooperated with the Safety Unit. It is structured at different levels in order to meet the needs ofdifferent categories of facility staff and researchers using the reactor. All personnel and visitors
entering the TRR-1/M1 receive training in radiation protection appropriate for their work/visit, or141

FNCA Consolidated Report on Radiation Safety (Thailand)

shall be escorted by an individual who has received such training. All personnel permitted
unescorted access in the TRR-1/M1 facility shall receive annual radiation safety refresher training.
Access controls are installed at various locations including the reactor gate, the reactor
building entrance, the reactor registration area, the water treatment area, the reactor gas tight area
and the refresh fuel storage room. All staff must be authorized at the level relevant to their workby the reactor manager and the head of the Safety Unit.
Emergency plans and procedures are implemented in two different levels, which are
emergency for operator in-house developed by reactor operation section and emergency
preparedness plan for institute (TINT) developed by the Safety Unit activated in the case of a
critical situation which Reactor Operators cannot handling. The training on emergency
preparedness is conducted once a year and is compliant with Ministerial Regulations
2.3 Radiation Safety in Radioactive Waste Management
Radioactive waste in Thailand is generated by R&D laboratories, the operation of a 2 MW
research reactor, nuclear medical applications, radio-pharmaceutical production, industries andothers. At present, Thailand has no nuclear power plants.
The Radioactive Waste Management Center (RWMC), Thailand Institute of Nuclear
Technology (TINT) has been separated from the Office of Atoms for Peace (OAP) to act as thecentralized radioactive waste management service in the country.
The main waste management facility is located in Chatuchak, a part of Bangkok. It is
composed of solid waste treatment facilities (such as incineration and compaction), liquid waste
treatment facilities (such as chemical precipitation and filtering systems) and storage facilities (seeTable 5.) Currently, there is no disposal facility in Thailand.
The nuclear regulatory function is conducted by the OAP. The RWM regulation and guidance
was first implemented in 2003, under the Atomic Energy for Peace Act B.E.2504 (1961) and theMinisterial Regulation on Rules and Procedures of Radioactive Waste Management B.E.2546(2003). Up to now, there are no specific regulations on licenses for radioactive waste operation
facilities.
2.3.1 Related law and regulation on Radiation Safety and Radioactive Waste Management
 The Atomic Energy for Peace Act B.E.2504 (1961)
 Ministerial Regulation on Condition and Procedure Requirements for License of the
Possession of Related Nuclear Materials, Radioactive Materials or Atomic Energy
B.E.2550 (2007)
 Ministerial Regulation on Rules and Procedures of Radioactive Management B.E. 2546
(2003) OAEP-1 Clearance Level of RW (Solid, Liquid and Gas) OAEP-2 Measure on Radiation Area OAEP-6 Measure on Safety of Radioactive material Nuclear material and
X-ray Working Area OAEP-7 Measure on Installation of Radiation Generator
 OAEP-10 Measure on Transportation of radioactive materials and wastes
 OAEP-18 Radiation Safety Officer
 OAEP-20 Guides of RW Segregation, Collection, Container and Label OAEP-21 Guides of Temporary Storage for RW Generator

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Table 5: Radioactive waste management facilities in Thailand
Items
Capacity
Facilities
Solid waste treatment Incinerator equipped with off gas
15 kg/hrcleaning system
Compactor
40 tonLiquid waste
Chemical precipitation plant
5 m3/batch
treatment
Stainless steel container
2 x 5 m3
Conditioning
In drum cement mixer
200 Liter
Storage

65 m2 x 4.5 m
81 m2 x 4 m
80 m2 x 4.5 m

Storage facility No.1
Storage facility No.2

300 m2 x 5 m

Storage facility No.3
(not at the Bangkok site, but in
Pathumthani Province)

Type of Waste
Burnable waste
Compactable waste
Aqueous waste with low
salt content
Organic liquid waste
Ash, sludge
Disused SRS
Treated Waste in drums;
ashes, sludge
Treated Waste in drums:
glass
Conditioned Radium indrums.
Newly coming disused
SRS

2.3.2 Safety assessment of Thailand Radioactive Waste Management Facility.
The TINT-RWMC (Radioactive Waste Management Center) has participated in several IAEA
international/regional projects. TINT- Radioactive Waste Management facility was selected to
be a Test Case under the IAEA Safety Assessment Driving to Radioactive Waste Management
Solutions. A methodology for preparing the safety case and safety assessment for predisposal
waste management facilities or activities is provided in IAEA Safety Guides DS284 . The
recommended approach to safety assessment is outlined in Figure 1. It includes the following key
components:(i)
Specification of the assessment context (including the purpose, scope, regulatory
framework, assessment endpoints, target audience, and philosophy of the assessment);(ii)

Description of the predisposal waste management facility or activity and waste, as
well the neighbouring areas;(iii)

Development, selection and justification of scenarios;(iv)

Identification and justification of models and data needs;(v)

Calculation, their verification and evaluation of results;(vi)

Analysis of safety measures and engineering, comparison against assessment criteria;(vii)

Independent verification of safety assessment results (by peer review and/or
independent assessment by Regulator), and(viii)

Review and modification of the assessment if necessary (iteration).

The steps outlined in Figure 2 are interdependent and should be performed in an iterative
manner. Solid black lines indicate the typical sequence of activities but this sequence is not

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mandatory. Dotted lines indicate possible changes to this sequence, for example if a hazard isscreened out there is no need for further modelling. Similarly the “Assessment Context” maychange as a result of subsequent stages in the safety assessment process.
Purpose,Regulations, Standards …

Assessment Context

Engineering Design

Description of Facility or Activity
and Waste

Safety Measures
Other relevant information(Management systems, operational

Develop and Justify Scenarios
Potential Hazard Identification

PIE lists, expert input
Existing risks

Hazard Screening
Identification of Scenarios

Generic Data
Existing models andcomputer codes

Identify Models and Data Needs

Perform Model Calculations
Evaluation of Results

Analysis of Safety Measures
Analysis of Engineering
Compare against Assessment
Criteria

Adequate

Acceptfor Safety
Case?

Independent
verification

Adequate?

ReviewandmodifyFig. 2: The Safety Assessment Process for Predisposal Waste Management

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2.3.3 Assessment Endpoints
The safety assessment takes the following endpoints into consideration for the normal
operation of the facilities:

The radiation exposure of workers in the waste management facilities is considered as an
endpoint to be compared to the worker dose limit.



Radiation exposure of the general public can arise from atmospheric releases and from aquatic
discharges. Respective endpoints for members of the general public are considered andcompared to the public dose limit.

For accident conditions, analogous endpoints are considered. These are not compared to any
quantitative criteria, however, but evaluated against the ALARA principle.

In accordance with the scope of the safety assessment, receptors for other endpoints than doseare not considered. Also, no endpoints relating to non-human species are taken into account since
this is not required by the current regulations.
2.3.4 Safety Management of Disused Sealed Source
There was a serious radiological accident in Thailand in 2000. The 400 Ci disused Co-60
teletherapy sources was cut open. The Co-60 source was dropped down in a scrap metal shop.
The OAP emergency team successfully recovered the source and then the subsequent
management, conditioning operation of the source have been successfully undertaken andcompleted in 2001.
During the year 2000-2002, Thailand team under advisement of an IAEA expert collected thedisused Radium-226 in the country and successfully conditioned all radium sources in the year
2004. In addition, the conditioning operation of 4 Ci Ra-226 external source was also
successfully conditioned by OAP team ( TINT at present) in the year 2005.
These conditioned sources are now safely stored at the TINT interim storage facilities awaiting
final disposal. The TINT- RWMC continues to pursue the upgrading of its centralized facility for
low to intermediate level radioactive waste treatment and storage facilities. Moreover, theTINT-RWMC in collaboration with other government agencies, such as MEXT/JAEA, FNCA,
KAERI, and US-DOE are co-operation for the safety management of radioactive waste
development projects.
2.3.5 Radiological Protection for Radiation Workers
The TINT ensures that the following dose limits will not be exceeded by TINT radiation
workers; an effective dose of 20 mSv per year averaged over five consecutive years.

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11. Vietnam
Part 1. Radiation Safety in Radiation Industry Facilities .......................................... 147
1.1 General ................................................................................................................. 147
1.1.1 Legislative framework and policy for radiation safety............................................. 147
1.1.2 Regulatory Body ................................................................................................. 148
1.2 Outline of Radiation Facilities and Radiation Sources ............................................... 148
1.2.1 Number of specialists and Workers in related organizations .................................... 148
1.2.2 Uses of radiation and nuclear in Vietnam............................................................... 149
1.3 Education and Training........................................................................................... 152
1.4 Standardization on Radiation and Radioactivity ........................................................ 153
Part2. Status of Radiation Safety Management ......................................................... 154
2.1 Radiation Safety Management System ..................................................................... 154
2.2 Radiation Safety Management................................................................................. 155
2.2.1 Radiological Protection for Radiation Workers....................................................... 155
2.2.2 Radiological Protection for Radiation area............................................................. 155
2.2.3 Radiological Protection for the Public ................................................................... 156
2.3 Emergency Plan for Radiation Accident ................................................................... 156
2.3.1 Plans for radiation incident response ..................................................................... 156
2.3.2 Responsibilities of related organizations individuals in case of incidents .................. 156
2.3.3 Training and Practical Exercises ........................................................................... 157
2.4 Radiation Safety Management in Radioactive Waste Management ............................. 157
2.4.1 Radioactive Waste Management ........................................................................... 157
2.4.2 Site selection for Low Level Radwaste Central Facility .......................................... 157

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11. Vietnam
Part 1. Radiation Safety in Radiation Industry Facilities
1.1 General
Now in Vietnam, radiation and radioisotopes have been applied in health care, agriculture,industry, geology, mining, meteorology, hydrology, transport, construction, oil and gas industry,
etc.
There is only one nuclear installation in the country is the Dalat nuclear research reactor withcapacity of 500 kW.
In order to meet the energy demand in the future, the first nuclear power plant (NPP) will be
put in operation in 2020 with capacity of 2000 MW and the second NPP with capacity of 2000
MW will be put in operation in 2021.
Atomic Energy Law had been approved at the twelfth National Assembly Session 3 on 3rdJune 2008 and come to enforce on 1st January 2009. The Atomic Energy Law includes 11
Chapters with 93 Articles.
1.1.1 Legislative framework and policy for radiation safety
According to articles 91, 103 of Statute of the Socialist Republic of Vietnam, the order oflegislative framework is as following:







Laws will be enacted by the National Assembly of the Socialist Republic of Vietnam.
Ordinances will be enacted by the Standing Committee of the National Assembly.
Decrees will be enacted by the Prime Minister of the Socialist Republic of Vietnam.;Circulars, Guidance, Codes of practices will be enacted by the Minister or some Ministers.
Atomic Energy Law, Article 6, Principles for activities and the assurance of safety andsecurity in the field of atomic energy.
Any activities in area of atomic energy shall ensure that public health, human life,
environment and social security are protected. State management on safety and security
shall be independent and scientifically based.

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1.1.2 Regulatory Body

Fig. 1: Structure and resources of regulatory body and supporting organizations

MOST: Under the Article 29 of Ordinance and the Article 34 of Decree 50/CP the MOSTE
was designated as the Regulatory Authority for Radiation safety and control. MOST is a
Regulatory Body being responsible to Government for the exercise of unified State management
over radiation safety and control throughout the country, responsible for organizing and directing
all radiation safety and control activities within the scope its function and duties.
VAEI: Under direction of the MOST, the VAEI is responsible for conducting all R&D
activities in the field of the application of nuclear energy in Vietnam and assisting the VARANSon technical aspects.
VARANS: Under direction of the MOST, the VARANS is responsible for building oflegislative documents, code of practice, procedures and regulations for radiation and nuclear
safety & control; organizing and implementing the notification, registration, license, renewal,
amendment and withdrawal of licenses for radiation and nuclear establishments,...; conducting
regulatory inspections on radiation and nuclear safety according to law.
DOST: The 63 Provincial Departments of Science & Technology (DOSTs)
are responsible for radiation protection and nuclear safety within the province under supervision
by VARANS.
1.2 Outline of Radiation Facilities and Radiation Sources
1.2.1 Number of specialists and Workers in related organizations
The number of people working with radiation related industry in Vietnam is difficult tocorrectly define however a number is available and is referenced in the VARANS’s report. In 2008,
there are more than 5,300 radiation workers belong to radiation installation and related148

FNCA Consolidated Report on Radiation Safety (Vietnam)

organisations. In the South, more than 3,500 radiation workers belong to radiation installation. In
the North, more than 1,800 radiation workers belong to radiation installation.
Currently the Service monitors approximately 6,000 workers. The results of personal exposure
are reported to VAEI and VARANS, to the supervisors of radiation workers.
1.2.2 Uses of radiation and nuclear in Vietnam
In 2006, MOST fulfill task for nation inventory of uses of radiation in Vietnam. There are 358
radiation facilities and 1,900 X-ray diagnose facilities. There are 2,136 radioactive sources and2,752 X-ray diagnose equipment.
The largest radiation facilities are:
- There is only one nuclear installation in the country is the Dalat nuclear research reactor withcapacity of 500 kW.
- One cyclotron 30 Mev built in 108 Military Hospital and operate in 2009.
There are two RWM facilities in Vietnam:- The system for RWM at the DNRI (Dalat Nuclear Research Institute) consists of two mainparts: The radioactive liquid waste treatment station and the disposal facilities.
- The Interim Storage Facility at the Institute for Technology of Radioactive and Rare Elements(ITRRE) at Phung, Hanoi City;
7%

2%
Industry

13%

Health Care
Education & Research
Others78%

Fig. 2: Percentage of radiation facilities in different areas

996

1007

133

Sources In
Use

Sources In
Storage

X-Ray

12

Accelerator

Figure 3: Number of radioactive sources and radiation equipment

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FNCA Consolidated Report on Radiation Safety (Vietnam)

Table 1: Number of facilities in health-careNo.
Application

1

Number of Facilities
In operation
Not in operation

Planned

14

3

2

2

Tele-therapy(sealed source)
Tele-therapy (accelerator)

6

-

-

3

Brachy-therapy (HDR)

3

2

-

4

0

4

-

5

Brachy-therapy (Low & Medium
dose rate)
X-Ray Diagnose

1900

-

-

6

Nuclear Medicine

23

-

1

7
8

Blood Irradiation
Radioisotope Production (cyclotron)

1
3

1
-

3
1

X-Ray

Unsealed
SourceAccelerator

Table 2: Number of sealed sources in health-careNo.
Application
Sealed Source

In UseIn Storage

1

Tele-theraphy

19

5

0

0

9

2

Brachy-therapy (HDR)

3

~15

2

0

0

3

0

658

0

0

0

4

Brachy-therapy (Low &Medium dose rate)
X-Ray Diagnose

0

0

2752

0

0

5

Nuclear Medicine

0

0

0

0

x

6
7

Blood Irradiation
Radioisotope Production

1
0

1
0

0
0

0
X

0
3 (Cyclotrons)

Number of Facilities

PlannedTable 3: Number of facilities in industry

No.

1Application

In operation

Not in operation

4

0

49

3

Sterilization Irradiation(sealed source)
Sterilization Irradiation(accelerator)
NDT (X-ray)

33

0

4

NDT (radioactive source)

23

0

5

Gauge (fix)158

6Well loging

12

0

7

Tracer1

0

8

X-ray fluorescent analysis

59

0

9

Main-board Scanner

1

0

2

150

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FNCA Consolidated Report on Radiation Safety (Vietnam)

Table 4: Number of sources in industry

No.

Application

Sealed Source

X-Ray

Unsealed
SourceAccelerator

1

Sterilization Irradiator

6

0

0

0

2

2

NDT

67

>180

50

0

0

3

Gauge

422

71

51

0

0

4

Well loging

88

30

0

x

0

5

Tracer

0

0

0

X

0

6

X-ray fluorescent analysis

59

0

18

0

0

7

Main-board Scanner

0

0

7

0

0

Table 5: Number of facilities in education, research& others

No.

Application

Number of Facilities
In operation
Not inoperation

PlannedEducation & Research
1

Education & Research

27

0

Others1Agricultural irradiators

0

2

2

Geology

1

3

3

X-Ray scanner (security & 8
customs)
Radiothermal
generators 0(RTG’s)

0

4

0

151

1 gamma field (DaLat)

FNCA Consolidated Report on Radiation Safety (Vietnam)

Table 6: Number of sources in education, research& others

No.

Application

Sealed Source

X-Ray

Unsealed
SourceAccelerator

11

X

1

In UseIn
Storage

327

105

0

2

4

120

0

x

0

Education & Research
1

Education & Research

Others1Agricultural irradiators
2

Geology3

X-Ray scanner (security & 0
customs)

0

97

0

0

4

Radiothermal(RTG’s)

0

0

0

0

generators 0

1.3 Education and Training
The radiation workers and the personnel having frequent access to Radiation Facilities shalltake appropriate radiation protection training courses in both the theoretical and practical aspects
to acquire radiation-handling skills needed for radiation worker, or for access to controlled areas.
- Training trainers- Establishing training programme for RPO, radiation workers- Conducting the courses for radiation protection and radiation measurements- Conducting training courses on Licensing and inspection for 128 staffs from 63 DOST, who
are in charge of radiation protection in provinces/cities
Table 7: Type of sevices

No.

Type of Services

1

Providing personal Dosimeter22

Calibration of Radiation Survey meter

2

3

Radiation Monitoring (measuring the dose 21
rate)
Calibration of X-ray Machine in Health 17
Care
Training in the radiation protection
VAEI + VARANS + DOSTs

4
5

Number of Facilities*National Education and Training on Nuclear Safety
The Hanoi National University (HNU) which is the largest university in Viet Nam to provide
human resources related to nuclear activities has a Department of Nuclear Physics. This
department was established in 1956 and currently produces around 50 graduates annually with a152

FNCA Consolidated Report on Radiation Safety (Vietnam)

basic degree in nuclear physics.
The Hanoi University of Technology (HUT) has a Department of Nuclear Engineering andEnvironmental Physics. The department was established in 1970 and currently produces about 20
graduates annually with a basic degree in engineering.
Dalat University is the other university which offers courses on nuclear science and it
produces about 20 graduate students annually.
1.4 Standardization on Radiation and Radioactivity
Radiation safety and radioactive waste management must be based on the reliable andprecise measurement of the quantities associated with ionizing radiation such as dose (Sv) an
radioactivity (Bq). For radiation safety, various dose meters are being used such as passive
dosimeters for personal dose and survey meters for ambient dose. Dose meters must be calibrated
regularly and always must show a right value in order to ensure the safety and security of thepeople related to ionizing radiations. Measuring instruments such as ionization chambers,
scintillation counters and semiconductor detectors are important in radioactive waste management,
which need to be calibrated using refernce radioisotope sources.
In the personal dosimetry network, VAEI and VARANS are presented as authority. In thisnetwork, there are two recognized personal dosimetry service centers: INST (Hanoi) and NRI(Dalat), which will provide individual monitoring service for the radiation workers in the wholecountry.
- In the South, more than 3,500 radiation workers belong to radiation installation are
examined annually. Read-out frequency: Once in 3 months and in 1 month (for someorganization).
- In the North, more than 1,800 radiation workers belong to radiation installation are
examined annually. Read-out frequency: Once in 3 months and in 1 month (for someorganization).
The results of personal exposure are reported to VAEI and VARANS, to the supervisors ofradiation workers.
Secondary Standard Dosimetry Laboratory (SSDL)
INST(Hanoi) operates and maintains a SSDL for national standard radiation dosimetry andcalibration of radiation protection instruments such as survey meter, pocket dosimeter but it islimitied in scale.
Intercomparison and international supports in increasing accuracy and personal dosimetry
management are essential. The intercomparisons were good way and very useful for finding the
problems in our system and help us to gain confidence and improve the accuracy of personal dose
equivalent estimation.

Figure 4: The TLD Reader
HARSHAW 4500

Figure 5: Calibration Instruments

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Part2. Status of Radiation Safety Management
2.1 Radiation Safety Management System
The Ministry of Science and Technology (MOST) is the Regulatory Body responsible for theunified State management of radiation protection and nuclear safety throughout the country;
organizing and directing all radiation and nuclear safety activities
The management of radiation safety within various radiation facilities is governed by the
specific standards, codes and guides.
These encompass all radiation management consideration for research, industrial and medical
related facilities as follows:
Table 8: List of Vietnam standards on radiation safety

1.

TCVN 3727 - 82

2.
3.
4.
5.
6.
7.

9.
10.
11.

TCVN 1638 - 75
TCVN 4397 - 87
TCVN 4498 - 88
TCVN 4985 - 89
TCVN 5134 - 90
TCVN 6053 – 95
(ISO 9696:1992)
TCVN 6053 – 95
(ISO 9697:1992)
TCVN 6561:1999
TCVN 6730-1:2000
TCVN 6866:2001

12.

TCVN 6867:2001

13.

TCVN 6868:2001

14.
15.

TCVN 6869:2001
TCVN 6870:2001

16.

TCVN 7077:2002(ISO 1757:1996)
TCVN 7078-1:2002(ISO 7503-1:1988)

8.

17.

18.

TCVN 7173:2002(ISO 9271:1992)

19.

TCVN 7174:2002(ISO 9271:1992)

Radioactive Wastes, Radioactive Dirt, Decontamination,
Radioactive sol – Glossary
Symbol on electrical diagram. Ionizing radiation detector
Ionizing radiation safety standards
Collective protection measures against ionizing radiation
Safe Transport Standards of Radioactive Materials
Radiation safety – Glossary
Water quality – Total amount of beta radiation measurement in
unsalted water – Thick-source method
Water quality – Total amount of beta radiation measurement in
unsalted water
Radiation Protection for Medical Installations
X-ray shielding materials – Lead rubber
Radiation Safety – Occupational Radiation Dose Limits forradiation worker and publicRadiation Safety – Safe Transport of Radioactive Materials –Part 1: General Provisions
Radiation Safety – Safe Management and Treatments ofradioactive Wastes – Classification of Radioactive Wastes
Radiation Safety – Medical exposure – General Provisions
Radiation Safety – Exemption of declaration, registration andlicensing
Radiation Safety – Personal photographic dosimeters
Radiation Safety – Evaluation of surface contamination – Part
1: Beta-emitters (maximum beta energy greater than 0.15
MeV) and alpha-emitters
Radiation Safety – Decontamination of radioactively
contaminated surfaces – Testing of decontamination agents for
textilesNuclear Energy – Radiation protection – Individual thermo
luminescence dosimeters for extremities and eyes

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2.2 Radiation Safety Management
VARANS: Under direction of the MOST, the VARANS is responsible for building oflegislative documents, code of practice, procedures and regulations for radiation and nuclear
safety & control; organizing and implementing the notification, registration, license, renewal,
amendment and withdrawal of licenses for radiation and nuclear establishments,...; conducting
regulatory inspections on radiation and nuclear safety according to law.
2.2.1 Radiological Protection for Radiation Workers
An increase in a person’s exposure to ionizing radiation, even at low doses, is assumed toincrease the risk of harm to that person’s health. As such, all radiation industries and facilities are
required to implement a system of radiation protection which limits possible detrimental effects
arising from occupational radiation exposure. This ALARA approach involves the design ofprocesses in such a way as to minimise exposure and to ensure that occupational dose limits are
met. Radiological protection is achieved through the following hierarchy:- avoidance of exposure, where practicable;- isolation of sources of radiation, where practicable, through shielding,- containment and remote handling techniques;- engineering controls, such as local exhaust ventilation to remove contaminants from theworkplace environment;- adoption of safe work practices, including work methods which make appropriate use oftime, distance and shielding to minimise exposure; and- where other means of controlling exposure are not practicable, the use of approved
personal protective equipment.
Radiation Protection of workers has to be monitored to make sure that the total amount of
external and internal exposure doesn’t exceed yearly lilit of effective dose by personal a
dosemeter and regular medical check in accordance with the applied regulations.
Table 9: Radiation dose limits for radiation worker

Application
Effective dose

Dose limit
Occupational
Public20 mSv per year, averaged 1 Sv in a year
over a period of 5 consecutive
calendar years

Annual equivalent dose in
the lens of the eye
150 mSv
the skin
500 mSv
the hands and feet
500 mSv
Reference: Occupational Radiation limits for radiation worker was given by TCVN 6866:2001.
About 6,300 of radiation workers in the country are monitored occupational dose. The duties andresponsibilities of the radiation service centers and radiation institution were defined by the Atomic Energy
Law 1, 2009.

2.2.2 Radiological Protection for Radiation area
Work processes and areas are designed to keep radiation exposure to a minimum. Where thepotential for exposure to radiation or contamination still exists, shielding and mechanical155

FNCA Consolidated Report on Radiation Safety (Vietnam)

ventilation are employ to minimise the dose received. Areas are classified according to thepotential radiation and contamination level.
Dose and contamination surveys are carried out by Radiation Safety Officer (RSO) as
schduled and also at request.
2.2.3 Radiological Protection for the Public
Monitoring for radionuclieds is carried out continually to determine compliance with the limits
imposed by the regulator and to fulfil the duty to protect members of the public. 03 Environmental
radiation monitoring stations have been established under the environmental surveillance
programme of the Ministry of Resources and Environment.
- 01 station in Dalat Nuclear Research Institute- 01 station in Ho Chi Minh City (belong to Dalat NRI)
- 01 station in Hanoi (INST)- Monitoring points in Laocai, Lang Son, Quang Ninh
In future, number of stations will be increased. Environmental Monitoring will coverimportant areas of Vietnam including area for NPP construction.
2.3 Emergency Plan for Radiation Accident
2.3.1 Plans for radiation incident response
Organizations, individuals conducting radiation activities shall develop their plans forradiation and nuclear incident response.
Provincial People’s Committee shall develop provincial plans for radiation and nuclear
incidents response; the MOST shall provide guidance on planning and approving the provincial
plans for radiation and nuclear incidents response.
The MOST shall collaborate with the Ministry of Industry, Ministry of Health, Ministry of
Defense, Ministry of Public Security, Provincial Peoples’s Committees in which radiation
facilities, nuclear facilities are operating and related organizations and individuals to develop
nationals plans for radiation and nuclear incident response to submit to the Prime Minister for
approval.
In advent of extremely severe incidents that may cause serious disaster, the emergency
announcement and response plan shall be executed in accordance with the law on emergency.
2.3.2 Responsibilities of related organizations individuals in case of incidents
1. Responsibilities of organizations, individuals conducting radiation practices:- Mobilising forces and means within the facilities to overcome incidents, mitigate the out
spread and consequences, conduct first-aid to injured persons, isolate the dangerous areas,and execute security control measures;- Providing information, documents and supports for remedy and investigation of the cause of
the incident.
2. Responsibilities of the agencies, organizations, superior to the organizations, individuals
conducting radiation activities:
3. Responsibilities of Province People’s Committtees:
4. Responsibilities of the Ministry of Science and Technology:
5. Responsibilities of the National Committee for Search and Rescue:
6. Responsibilities of the Ministry of Defense:156

FNCA Consolidated Report on Radiation Safety (Vietnam)

7. Responsibilities of the Ministry of Public Security, The Ministry of Foreign Affairs, The
Ministry of Public Health, related organizations, individuals.
2.3.3 Training and Practical Exercises
Medical response in the case of Radiological Emergencies:- Training – about 50 hours every year for pre-hospital radiation emergency response team
- Exercises – Each Team consists about 12-15 responders and has Lectures and Practical
exercises every three months- Drill – often have one radiation emergency drill on-site per year with different scenarios.
National Training Course of Front Line Control with practical exercises for detection and responsein the case of illicit trafficking and incident/accident on import/export control.
Drill/Exercises for VAEI and Hanoi local officials: missing sources accident.
Improved DNRR Emergency Plan: include fresh fuel transportation for conversion program.
2.4 Radiation Safety Management in Radioactive Waste Management
2.4.1 Radioactive Waste Management
Radioactive waste in Vietnam is generated by research, industry, medical applications,research reactor operation and radiopharmaceutical production. Naturally occuring radionuclides(NORM) and tecnologically enhanced naturally occuring radioactive materials (TENORM) areproduced in Vietnam by the mining, mineral sands processing and other resources sectors.
Vietnam has no nuclear power plants.
There are two RWM facilities in Vietnam:- The system for RWM at the DNRI (Dalat Nuclear Research Institute) consists of two mainparts: The radioactive liquid waste treatment station and the disposal facilities.
+ The radioactive liquid waste treatment station: collected and treated liquid radwastes
from reactor operation, radioisotope production and other laboratories.
+ The disposal facilities collected, treated and stored dry and wet solid radwastes. In thesefacilities, eight concrete pits have been constructed for disposal and solidification offradioactive waste.
- The Interim Storage Facility at the Institute for Technology of Radioactive and Rare Elements(ITRRE) at Phung, Hanoi City. In this facilities, all radioactive waste from ITRRE and otherInstitute in the North of Vietnam are collected, classified, treated and stored in interim storage.
2.4.2 Site selection for Low Level Radwaste Central Facility
On the 3rd of January 2006, the Prime Minister has approved the Strategy for Peaceful Uses ofAtomic Energy up to 2020 in Vietnam. According to that, Vietnam will set up the first nuclear
power plants in 2020 year. Site selection for low level radioactive waste repository is essential task
for activities in the fields of atomic energy and for NPP in future. Office studies on
meteorological, geological and hydrogeological conditions of Vietnam show that on the territoryof Vietanm, the only Coastal Region of South-Central Area might be considered as relevant andthe most suitable region for construction of the future national near surface disposal facility of
low and intermediate levels radioactive wastes.
There are 03 most suitable candidate sites: TuThien village, SonHai village, NinhPhuoc
district and Thai An village, Ninh Hai district, NinhThuan Province.

157

IV. Contributors
Australia
Mr. Lubi Dimitrovski
Australian Nuclear Science & Technology Organisation (ANSTO)

Bangladesh
Dr. M. Moinul Islam
Bangladesh Atomic Energy Commission (BAEC)

China
Dr. Zhang Jintao
China National Nuclear Corporation (CNNC)

Indonesia
Dr. Syahrir
National Nuclear Energy Agency of Indonesia (BATAN)

Japan
Prof. Toshiso Kosako
The University of Tokyo
Mr. Akira Suzuki
Tokyo Electric Power Company
Dr. Hideki Harano
National Institute of Advanced Industrial Science and Technology (AIST)
Mr. Hiroyuki Murakami
Japan Atomic Energy Agency (JAEA)
Mr. Seiichi Kudo
Mitsubishi Heavy Industries, Ltd
Dr. Shouji Futatsugawa
Japan Radioisotope Association (JRA)Dr. Takatoshi Hattori
Central Research Institute of Electric Power Industry
Dr. Takeshi Iimoto
The University of Tokyo
Mr. Teruyoshi Iizuka
Toshiba Corporation
Mr. Tomohiro Kuroki
Fuji Electric Systems
Mr. Toshiharu Miyakawa
Japan Nuclear Fuel Limited (JNFL)

Malaysia
Dr. Mohd Abdul Wahab Yusof
Malaysian Nuclear Agency (Nuclear Malaysia)

The Philippines
Ms. Maria Visitacion B. Palattao
Philippine Nuclear Research Institute (PNRI)

158

Thailand
Ms.Nanthavan Ya-anantThailand Institute of Nuclear Techonology (TINT)
Mr. Sutat Thiangtrongjit
Thailand Institute of Nuclear Techonology (TINT)

Vietnam
Dr. Le Ba Thuan
Vietnam Atomic Energy Institute (VAEI)

Edited by Nuclear Safety Research Association (NSRA)FNCA Secretariat(As of March 2012)159