FNCA Consolidated Reporton Radiation Safety

March 2014
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 ...........................................................................10
2. Bangladesh .........................................................................................................................................23
Part 1. Radiation Safety in RI Facilities ........................................................................................24
Part 2. Status of Radiation Safety Management ...........................................................................29
3. China...................................................................................................................................................37
Part 1. Radiation Safety in RI Facilities ........................................................................................38
Part 2. Status of Radiation Safety Management ...........................................................................44
4. Indonesia ............................................................................................................................................53
Part 1. Status of Radiation Safety Management ...........................................................................54
5. Japan...................................................................................................................................................56
Part 1. Radiation Safety in RI Facilities ........................................................................................57
Part 2. Status of Radiation Safety Management ...........................................................................70
6. Kazakhstan ........................................................................................................................................95
Part 1. Radiation Safety in RI Facilities ........................................................................................96
Part 2. Status of Radiation Safety Management .........................................................................101
7. Malaysia ...........................................................................................................................................103
Part 1. Use of Radiation Sources and Radiation .........................................................................104
Part 2. Status of Radiation Safety Management ......................................................................... 111
8. Mongolia...........................................................................................................................................121
Part 1. Radiation Safety in Radioisotope Facilities ....................................................................122
9. The Philippines................................................................................................................................134
Part 1. Radiation Safety in Radioisotope Facilities ....................................................................135
Part 2. Status of Radiation Safety Management ......................................................................141
10. Thailand .........................................................................................................................................150
Part 1. Radiation Safety in Radioisotope Facilities ....................................................................151
Part 2.Status of Radiation Safety Management ..........................................................................156
11. Vietnam...........................................................................................................................................171
Part 1. Radiation Safety in Radiation Industry Facilities ...........................................................172
Part2. Status of Radiation Safety Management ..........................................................................180

IV. Contributors............................................................................................................................ 187

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 2014.
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 withthe aim of promoting the application of nuclear technology through collaboration among
Asian countries. During this period the sharing of information, exchanges of scientificpersonnel and active 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

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,
and various other fields is rapidly increasing, and at the same time, several countries arelooking into introducing nuclear power plants. In consideration of such tendency, member
countries have been 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 asa serried 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]

iii

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 ...................................... 4
1.2.1 Number of Specialists and Workers in Related Organizations ........................................... 4
1.2.2 Number of Radiation Facilities including Related Facilities .............................................. 4
1.2.3 Activity and Number of Radiation Sources and Generators ............................................... 5
1.2.4 Radiation Source Management and Disposal ..................................................................... 5
1.3 Education and Training ........................................................................................ 6
1.3.1 Radiation Industry Usage..................................................................................................... 6
1.3.2 Radiological Protection........................................................................................................ 9
1.4 Standardization on Radiation and Radioactivity.............................................. 10Part 2. Status of Radiation Safety Management ................................................................................. 10
2.1 Radiation Safety Management in various Radiation Industries ..................... 10
2.1.1 Radiation Safety Management System.............................................................................. 10
2.1.2 Radiological Protection for Radiation Workers................................................................. 11
2.1.3 Radiological Protection for Radiation Area....................................................................... 12
2.1.4 Radiological Protection for the Public............................................................................... 13
2.1.5 Radiation Emergency Preparedness .................................................................................. 13
2.2 Radiation Safety Management in Research Reactors ...................................... 15
2.2.1 Radiation Safety Management System.............................................................................. 15
2.2.2 Radiological Protection for Radiation Workers................................................................. 15
2.2.3 Radiological Protection for Radiation Area....................................................................... 16
2.2.4 Radiological Protection for the Public............................................................................... 17
2.2.5 Radiation Emergency Preparedness .................................................................................. 17
2.3 Safe Management of Radioactive Waste............................................................ 18
2.3.1 Radiation Safety in the Management of Radioactive Waste ............................................. 19
2.3.2 Radiological Protection for Radiation Workers................................................................. 21
2.3.3 Radiological Protection for Radiation Area....................................................................... 21
2.3.4 Radiological Protection for the Public............................................................................... 21
2.3.5 Radiation Emergency Preparedness .................................................................................. 22

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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 jurisdictionin Australia and is in compliance with the IAEA BSS and IAEA GS-R-1. A committee
comprised of Commonwealth 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
such as the environmental protection authorities and health departments in each state.
Table 1: Legislative jurisdictions, Regulators and Regulations

Jurisdiction
New South Wales
Australian
Territory
Victoria
Tasmania

Regulator

NSW Environment
Authority
Capital ACT HealthSouth Australia

Western Australia

Queensland
Northern Territory
Federal government

Acts/Regulations
Protection Radiation Control Act 1990, Radiation Control
Regulation 2013Same as Federal government

Department of Health
Dept of Health and Human
Services
Environment Protection Authority

Radiation Act 2005, Radiation Regulations 2007
Radiation Protection Act 2005 and Radiation
Protection Regulations 2006
Radiation Protection and Control Act 1982,
Radiation Protection Control (Ionising Radiation)
Regulations 2000, Radiation Protection andControl (Transport of Radioactive Substances)
Regulations 2003
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 Health
Radiation Safety Act 1999, Radiation Safety
Regulation 2010.
Department of Health
Radiation Protection Act 2012, Radiation
Protection Regulations 2012.
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
in organisations 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 themanagement of nuclear activities and storage of radioactive waste at Commonwealth agencies
such as the Australian Nuclear Science and Technology Organisation (ANSTO), theCommonwealth Science Industry and Research Organisation (CSIRO) and the Department of
Defence.
Radiation protection legislation typically includes the following areas:

Setting maximum dose limits

Licensing of people to use radioactive substances or apparatus

Registration of radiation emitting equipment

Safety procedures

ResponsibilitiesPowers of inspection for the regulator



Enforcement provisions and penalties

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 codesand standards on radiation protection have been issued by ARPANSA as the Radiation
Protection Series and provide guidelines for handling, processing, transport and disposal ofradioactive 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 2011 for
adoption by the States and Territories.
Within ARPANSA, the Radiation Health and Safety Advisory Council (RHSAC) wasestablished under the Australian Radiation Protection and Nuclear Safety Act 1998 (ARPANS Act)with the following core objectives:

To identify emerging issues and matters of major concern to the community in relation toradiation protection and nuclear safety;

To provide high level advice to the CEO of ARPANSA on issues relating to radiation
protection and nuclear safety; and3

FNCA Consolidated Report on Radiation Safety (Australia)To support the development of Codes, Standards and Guidance that promotes radiation
protection and nuclear safety.

As such, the RHSAC publishes statements providing advice on a range of current radiation
health and safety issues relating to medical radiation, radioactive waste and radiation
protection.
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 in radiation related industries in Australia is difficult tocorrectly define. ARPANSA provides a Personal Radiation Monitoring Service (PRMS) thatenables radiation workers to monitor the radiation dose received in their occupations. Currently
the Service monitors approximately 35,000 workers (approximately 70% of occupationally
exposed persons in Australia) and maintains dose histories for over 125,000 people. The
assessment of doses received by radiation workers enrolled in the PRMS is listed according totheir occupational classification (including numbers of staff monitored) in the ARPANSA
Technical Report 139, “Personal Radiation Monitoring Service and Assessment of Doses
Received by Radiation Workers (2004)”. Table 2 indicates that there are more than 5,800
organisations (medical and non-medical) registered to possess a radiation source or radiation
apparatus in Australia. The number of work sites may be considerably more as one businesslicence can be given for multiple sites.
Table 2: Number of Registrations of organisations working with radiation apparatus/sources in Australia

Regulator

NSW
VIC
QLD
SA
WA
TAS
ACT
Commonwealth
TOTAL

Total
(medical and non-medical)
242
335
2500
172
2050
n/a
433
93
5825

Estimated registeredorganisations inindustrial field
50
12
400
35
1574
17
87
20
2195

NB: The data presented in the above table is indicative only, as it is gathered from different data
sources in different years and makes assumptions about the extent of industrial radiation activity ineach state which may not be correct for some jurisdictions.

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 seven cyclotron facilities in operationin Australia: two in Victoria (Austin Hospital and Cyclotek), three in NSW (Royal Prince Alfred

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FNCA Consolidated Report on Radiation Safety (Australia)

Hospital, Sydney, Brain and Mind Research Institute, Sydney and PETNET, Sydney), one inWestern Australia (Sir Charles Gairdner Hospital, Perth) and one in Queensland (RoyalBrisbane and Women's Hospital). There are around 100 linear particle accelerators Australia
wide which are located in cancer treatment facilities. There are also 3 commercial facilities forthe irradiation of food which are located in NSW, Queensland and Victoria.
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(GATRI).

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.
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. 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 withsolid tumours. Category 1 Co-60 and Cs-137 teletherapy sources are among the higher activity
sources in general use (37- 560 TBq and 19 – 56 TBq respectively).
Radioactive sources are also used in education and research and contain a wide variety ofradionuclides including Co-60, Cs-137 and Am-241. Industrial applications typically use Ir-192 (0.19-7.4 TBq) for non-destructive imaging of pipe welds. Co-60 sources are also used for industrial
radiography (0.41 – 7.4 TBq). Category 3 neutron and gamma sources are used in mining, as well as
in oil and gas well logging. The most common industrial radioactive sources are used in level andthickness gauges and in process control.
1.2.4 Radiation Source Management and Disposal
Within Australia, radioactive sources are managed by the licence holders according to therequirements of the regulator within their jurisdiction. In many jurisdictions it is a regulatory
requirement that radioactive sources for which there are no foreseen use should be returned wherever
possible to the supplier, either for recycling or disposal. In some states there are small disposal
facilities where waste sources are held (Table 6). Whilst Australia does not lack the necessary
infrastructure to manage its disused sources the absence of a centralised storage or disposal facility forsuch radioactive sources is not ideal. In the RHSAC Scoping Review of Issues Related to theManagement of Intermediate Level Radioactive Waste in Australia (2011), it states that “The longterm storage of radioactive waste at many sites throughout Australia, without a clearly defineddisposal pathway, leaves the potential for significant health, safety and environmental issues to arise.
These include occupational health risks in the management of radioactive waste, public health risks
and security issues. For example, security of sources is a significant consideration when waste isstored at many sites, as it may lead to a high risk of orphan (lost, stolen or abandoned) sources and thepotential for serious accidents, safety and security risks.”

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FNCA Consolidated Report on Radiation Safety (Australia)

From 2004 – July 2013 ANSTO coordinated and funded the S-E Asia Regional Security ofRadioactive Sources Project (RSRS) to address awareness of poorly controlled or vulnerable
radioactive sources in S-E Asia and the Pacific, a lack of border controls, detection capability andregulation. The goal of the ANSTO project was to prevent acquisition of sources by unauthorised
persons, and prevent serious accidents from uncontrolled sources. The strategy of the RSRS project
was to “enhance the technical and organisational capacity and capability of partner countries’
government organisations and other entities to develop and deliver their own effective andsustainable programs for the physical protection and security management of radioactive sources andtheir associated facilities, and for radiological emergency preparedness and response, consistent withinternational standards and guidance.” Implementation of the strategy specifically involved
strengthening regulatory and legislative controls, applying standards and training regulators,
developing capabilities in equipment and provision of training in their operation, and identification
and addressing of situations involving vulnerable or orphan radioactive sources. Outcomes of the
project in cooperation with counterparts in South East Asia included:


Development, implementation and updating of specific source security regulations andassociated standards, codes and guidance in several countries.



Regular development and conduct of training courses and training development
workshops, including practical exercises, with support provided to the country’s relevant
agencies for subsequent development and conduct of their own training programs.

Regulators and operators implementing their respective roles and responsibilities for
ensuring the requirements for physical protection and security management of radioactive
sources, such as facility security plans, are satisfied.



Peer-review of regulators’ and operators’ practices and materials, and the development of
new materials by the country’s relevant agencies.

Regular development and conduct of practical exercises and the provision of radiation
detection, monitoring and identification equipment for use in orphan source searches, andin preparation for and response to “dirty bomb” or sabotage situations.

This project ended in July 2013, however there remains an on-going need to raise and maintainawareness of the need to protect and control radioactive sources from a radiation safety and security
viewpoint.
1.3 Education and Training
1.3.1 Radiation Industry Usage
The ARPANSA National Directory for Radiation Protection requires that all occupations
and professions who use radiation sources meet the relevant professional competency
requirements. In most cases, competency is evidenced by formal qualification in their field andradiation 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 andchiropractors. Industry related occupations include industrial radiographers, borehole loggers,
radiation source testers and persons servicing, installing, commissioning, maintaining, repairing

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FNCA Consolidated Report on Radiation Safety (Australia)

or manufacturing radiation sources. The evidence of qualification required for each of theseoccupations is listed in RPS 6 National Directory for Radiation Protection. An example is givenin the table below.
Table 3: Authorisation to use Radiation Sources for Specified Practices – taken from Schedule 6 of the National
Directory for Radiation Protection

Occupation/Practice

Required Evidence of Qualification

Use of X-ray equipment by − graduates in Chiropractic from RMIT University, Bundoora,
chiropractors for plain film Victoria (or forerunner Phillip Institute of Technology)
diagnostic radiography of the− graduates in chiropractic from Macquarie University, NSW (orspine and pelvis
forerunner Sydney College of Chiropractic, Ashfield, Sydney, NSW
since 30 Nov 1983)− For overseas trained chiropractors, one of the following:− satisfactory assessment by RMIT University or Macquarie
University− individual Assessment by the relevant State/Territory Authority
against a protocol agreed by the Radiation Health Committee
Useofintra-oral
X-ray − current registration by the relevant Dental Board
equipment by dentists forradiography of teeth and facial
bones
Use
of
intra-oral
X-ray − current registration as a dental hygienist by the relevant Dental
equipment by dental hygienists Board; and one of the following:
for dental radiography− Diploma of Dental Hygiene from Oral Health Centre of WA or
Torrens Valley College of TAFE (Gilles Plains SA)− for Overseas trained dental hygienists, satisfactory assessment
from Oral Health Centre of WA or Torrens Valley College of TAFE
(Gilles Plains SA)
Useof
intra-oral
X-ray − current registration as a dental therapist by the relevant Dental
equipment by dental therapists Board, and satisfactory assessment at course in dental therapy
for dental radiography
accredited by the Authority.
Use of X-ray equipment by Must provide evidence of one of the following:
diagnostic radiographers for• Australian Institute of Radiography (AIR) Statement of
diagnostic radiography
Accreditation (AIR Statement of Accreditation)• Certificate of Competence issued by the Conjoint Board of theRoyal Australasian College of Radiologists (RACR) and the AIR• Diploma of Qualification issued by the Conjoint Board of the
RACR and the AIR• 1984 Assoc. Diploma in Diagnostic Radiography Graduates from
Sydney TAFE

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FNCA Consolidated Report on Radiation Safety (Australia)

Persons undertaking the Professional Development Year (PDY) at an
accredited institution or practice must provide evidence of thefollowing to obtain a restricted authorisation:• AIR Provisional Statement of Accreditation
Use of radiation equipment by Must provide evidence of one of the following:radiation therapists for radiation• AIR Statement of Accreditation in therapeutic radiography(AIRtherapy
Statement of Accreditation)• Certificate of Competence in therapeutic radiography issued by the
Conjoint Board of the RACR and the AIR• Diploma of Qualification in therapeutic radiography issued by the
Conjoint Board of the RACR and the AIR
Persons undertaking the Professional Development Year (PDY) at an
accredited institution or practice must provide evidence of thefollowing to obtain a restricted authorisation:• AIR Provisional Statement of Accreditation
Use of radioactive materials by Must provide evidence of the following:
nuclear medicine technologists• Statement of Accreditation by ANZSNM
for nuclear medicine purposes
Persons undertaking the Professional Development Year (PDY) at an
accredited institution or practice must provide evidence of thefollowing to obtain a restricted authorisation:• Provisional Statement of Accreditation from Australian and New
Zealand Society of Nuclear Medicine (ANZSNM)
Use of radiation sources by • diagnostic X-ray equipment use for small animal radiography
veterinary
surgeonsfor− current registration by the relevant Veterinary Board
veterinary purposes• sealed radioactive source use:
− current registration by the relevant Veterinary Board, andsatisfactory completion of an accredited examination on theprinciples and practices of radiation protection in the proposed use ofradioactive materials• unsealed radioactive source use:
− current registration by the relevant Veterinary Board, andsatisfactory completion of an accredited examination on theprinciples and practices of radiation protection in the proposed use ofradioactive materials.

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FNCA Consolidated Report on Radiation Safety (Australia)

1.3.2 Radiological Protection
Education and training in radiation safety and radiological protection is provided bynumerous companies, health departments and institutions within Australia with training
providers and formal training courses approved by the relevant jurisdictional regulator. There
are around forty providers of 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. ARPANSA have initiated a project with
Government Skills Australia to develop competency based training units in radiation safety forincorporation into radiation safety training programs. The objective of developing thesecompetencies was to establish a nationally consistent training and skills recognition system thatwould result in the delivery of courses to meet workplace requirements and recognize current
skills and competencies of employees already working in this area (who did not previously haveformal qualification in this area). These competencies are in alignment with the various levels of
qualifications offered in Australia’s Vocational Educational Training (VET) system which
operates under the Australian Qualifications Framework (AQF) for regulating the standard ofeducation across the country.
The Accreditation in Ionising Radiation Safety within Australia is administered by theAustralasian Radiation Protection Accreditation Board which is sponsored by the following
professional societies:• Australasian College of Physical Scientists and Engineers in Medicine (ACPSEM),• Australasian Radiation Protection Society (ARPS), and• Australian Institute of Occupational Hygienists Incorporated (AIOH).
Radiation Protection Advisors are accredited by the Australasian Radiation Protection
Accreditation Board following successful completion of the required set of practical andtheoretical components. In order to complete the theoretical component of the accreditation, thecandidate must satisfy the Board that he/she has a suitable level of education, complete a
self-paced reading and numerical problem solving program and pass a written examination
based on the prescribed reading material and the requirement for adequate skills in numericalcomputation. In order to complete the practical component of the accreditation, a candidate
must gain practical experience in the use of radiation monitoring equipment and complete an
assignment (approximately 5000 words) in which the candidate prepares a radiation
Candidates are usually recent graduates in science or engineering. The standard for
accreditation has been set so that the syllabus can be completed with part- time study to enableaccreditation within one year of taking up an appointment where the relevant experience isgained. Other graduates and non-graduates will be accepted as candidates provided they canshow adequate evidence that they have the ability to achieve the required entrance standard
which includes skills in physics, chemistry, mathematics, computation, anatomy and physiology.
Accreditation in Ionising Radiation Safety is for a period of three years. In order to maintaintheir accreditation for a further three years, candidates must demonstrate that they are actively
maintaining their expertise.

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FNCA Consolidated Report on Radiation Safety (Australia)

1.4 Standardization on Radiation and Radioactivity
Calibrations of dosimeters and radiation monitoring equipment through service providers aretraceable to national standards. ARPANSA and ANSTO dosimetry services have participated in
the IAEA/RCA intercomparisons study held under IAEA/RCA RAS/9/029 Harmonization ofRadiation Protection, Phase IV – RCA Project completed in 2008.
There may be varying radiation protection recommendations and exemption criteria acrossthe State/Territory jurisdictions (some are based on total activity and others are on activity
concentration). However, the approaches to radiation protection are generally consistent and thedose limits in line with those stated in the National Directory for Radiation Protection. Table 3
below summaries the current applicable dose limits.

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 and readily accessible on theirwebsite.
These encompass all radiation management considerations for research, industrial andmedical related facilities as follows:

Recommendations for Limiting Exposure to Ionizing Radiation (1995) and National
Standard for Limiting Occupational Exposure to Ionizing Radiation (republished 2002)(RPS 1)

Code of Practice for the Safe Transport of Radioactive Material (2008 Edition), Safety
Guide for the Safe Transport of Radioactive Material (2008 Edition) and Safety Guide forApproval Processes for the Safe Transport of Radioactive Materials (2012) - (RPS 2, 2.1
and 2.2)



Radiation Protection Standard for Maximum Exposure Levels to Radiofrequency Fields 3 kHz to 300 GHz (2002) - (RPS 3)

Recommendations for the Discharge of Patients Undergoing Treatment with Radioactive
Substances (2002) - (RPS 4)

Code of Practice and Safety Guide for Portable Density/Moisture Gauges Containing
Radioactive Sources (2004) - (RPS5)

National Directory for Radiation Protection, July 2011 - (RPS 6)

Recommendations for Intervention in Emergency Situations Involving Radiation
Exposure (2004) - (RPS 7)



Code of Practice for the Exposure of Humans to Ionizing Radiation for Research Purposes(2005) - (RPS 8)

Code of Practice and Safety Guide for Radiation Protection and Radioactive Waste

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FNCA Consolidated Report on Radiation Safety (Australia)

Management in Mining and Mineral Processing (2005) - (RPS 9)

Code of Practice and Safety Guide for Radiation Protection in Dentistry (2005) - (RPS 10)

Code of Practice for the Security of Radioactive Sources (2007) - (RPS 11)

Radiation Protection Standard for Occupational Exposure to Ultraviolet Radiation (2006)– (RPS12)

Code of Practice and Safety Guide for Safe Use of Fixed Radiation Gauges (2007) - (RPS 13)

Code of Practice for Radiation Protection in the Medical Applications of Ionizing
Radiation (2008), Safety Guide for Radiation Protection in Diagnostic and Interventional
Radiology (2008), Safety Guide for Radiation Protection in Nuclear Medicine (2008) and
Safety Guide for Radiation Protection in Radiotherapy (2008) - (RPS 14, 14.1, 14.2 and
14.3)



Safety Guide for the Management of Naturally Occurring Radioactive Material (NORM)(2008) - (RPS 15)



Safety Guide for the Predisposal Management of Radioactive Waste (2008) - (RPS 16)



Code of Practice and Safety Guide for Radiation Protection in Veterinary Medicine (2009)- (RPS 17)



Safety Guide for the Use of Radiation in Schools (2012) – (RPS 18)



Code of Practice for Radiation Protection in the Application of Ionizing Radiation by
Chiropractors (2009) – (RPS 19)



Safety Guide for Classification of Radioactive Waste (2010) – (RPS 20)

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. Radiologicalprotection 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.
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 4: 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
20 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 (Deleted in amendment)
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 topersonnel who may be occupationally exposed to radiation. Within medical facilities these are
implemented by a well-qualified workforce of medical and hospital physicists who interact wellwith each other through professional bodies.
Doses to radiation workers are measured either through thermoluminescent dosimeters orelectronic personal dosimeters. ARPANSA provides a national dosimetry service for some
35,000 radiation workers nationally on a cost recovery basis. Australian Nuclear Science andTechnology Organisation (ANSTO) provides an in-house service for 937 radiation workers.
There are also a number of other commercial personal dosimetry service providers(international companies based in Australia).
In 2011 Australia established the National Radiation Dose Register (ANRDR) to ensure thatrecords of a worker’s radiation dose are maintained in a centralised register regardless of where
the individual is working. The ANRDR is an electronic database designed to collect and store
radiation dose information for workers who are occupationally exposed to radiation. These
workers can request a record of their radiation dose history from the ANRDR. Currently, the
ANRDR only maintains records for workers in the uranium mining and milling industries
however expansion of the ANRDR to include workers exposed to radiation in other industries isin progress.
Within other industries, worker dose records are held by the operator and the dosimetry
service provider and this data is reviewed by the relevant regulator. ANSTO and ARPANSA
maintain whole body monitoring and bioassay radionuclide intake dose records for theirregistered individuals.
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
to carry out such monitoring for operators who do not have the required in-house expertise.

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FNCA Consolidated Report on Radiation Safety (Australia)

Radiological protection measures for specific radiation areas are implemented by the operatorsin order to comply with the relevant regulations.
Through their Radiation Health and Safety Advisory Council, ARPANSA have also
identified the need to assess the radiation levels in workplaces not normally associated withradiation activities and to provide technical support. These include potential radiation exposure
from:

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 3).
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
is provided 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) theevaluation of 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
specific potential threat situations. ARPANSA is the national 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:


Attorney Generals Department Crisis Coordination Centre (AGDCCC), 24h/d which ismanaged by Emergency Management Australia (EMA).

National Competent Authority - Australian Radiation Protection and Nuclear Safety
Agency (ARPANSA) - on call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.,)

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FNCA Consolidated Report on Radiation Safety (Australia)

Australian Defence Force (ADF)
The following plans are in place in the event of a radiological emergency:

Nuclear Powered Warships (NPW) accidents - OPSMAN1 (Defence Operations Manual
1 edition 9). The following plans are put into effect in escalating order: Port Safety Plans
 State plans and arrangements for NPW accidents
 EMPLANS or COMDISPLAN (Australian Government Disaster Response
Plan)



Accident/misuse of Radioactive/Nuclear material
 State/Territory response (most States/Territories have a Chemical, Biological,
Radiological, and Nuclear (CBRN) or HAZMAT equivalent State plan orState/Territory Emergency Plans (EMPLANS). If State/Territory resources
are tapped they can request additional national resources throughthe Attorney Generals Crisis Coordination Centre (AGCCC). This inevitably
invokes the COMDISPLAN.

Specific RN hazards
 Space debris re-entry (COMDISPLAN SPRED)
 Maritime R/N (COMMARRPLAN)
 Radiological/Nuclear Terrorism (National Counter-Terrorism Plan)International Response under Convention for Requesting Assistance

ARPANSA maintains two offices with Scientific (Melbourne) and Regulatory (Sydney) units.
Radiation Emergency Planning is coordinated by the Health Physics Section of the Environmental
and Radiation 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. The Collaborating
Centre is one of 13 centres internationally (Armenia, Australia, Brazil, France, Germany, Japan, theRussian Federation, United Kingdom, Ukraine and USA) that form the WHO Radiation Emergency
Medical Preparedness and Assistance Network (REMPAN). This role requires that ARPANSA
assist in training and dissemination of information on response to radiation accidents andemergencies, as well as respond to WHO requests for assistance for radiation accidents andemergencies in neighbouring countries. Specific objectives of Australia’s Collaborating Centre are to:help Member States in elaborating their plans for medical preparednesspromote training of personnel in developing countries in medical preparedness and firstaiddefine optimal methods for diagnosis or treatment of over-exposureprovide medical assistance to exposed persons both on site and in specialised clinics,

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FNCA Consolidated Report on Radiation Safety (Australia)

subject to bilateral agreement between Australia and the country(s) concerned.
ARPANSA and ANSTO both have accredited IAEA RANET (Response Assistance
Network) teams for assistance in international response to radiation emergency. ARPANSA
maintains an Australia-wide network of fallout monitoring stations as part of theComprehensive Test Ban Treaty (CTBT) network of monitoring stations.
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 isregulated by ARPANSA and its safety management system must comply with theirrequirements. ANSTO is dedicated to implementing international best practice in this area andadopts the relevant recommendations given by the IAEA. ANSTO has adopted an ALARA
approach to radiation exposure and have implemented a more stringent internal occupationaldose constraint of 15 mSv in comparison 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
2.1.2. 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 to assess 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 937 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 datacollected from thermoluminescent detectors is reviewed on a monthly basis by ANSTO’s
personal dosimetry service. Any anomalous or unusually high levels of effective dose areinvestigated to determine the cause of exposure. Through this process of review andinvestigation, improvements to practices and equipment are identified and implemented in orderto prevent continued or potential abnormal high exposure. Radiation workers at ANSTO arealso equipped with electronic personal dosimeters which are used to measure their cumulative
dose during a certain task or over the 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.

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FNCA Consolidated Report on Radiation Safety (Australia)

Radiation workers are equipped with the personal protective equipment (PPE) required forthe particular work area (depending on its radiation classification) and for specific tasks. Inclassified 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.
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
with HEPA filtration are employed to minimise the dose received. Areas are classified according to
the potential radiation and contamination level.
Table 5: 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

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

Table 6: 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 toraise an alarm when an upper radiation set point has been reached to alert personnel to discontinue theprocess, make safe or evacuate. Red and Blue contamination classified work areas are also equippedwith contamination detectors for checking personnel on exiting the area. All contamination andradiation monitors are calibrated annually by ANSTO’s calibration services.
Dose and contamination surveys are carried out by health physics surveyors as scheduled andalso 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 the receiver of the item’s dose, contamination level and any special handling requirements.

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FNCA Consolidated Report on Radiation Safety (Australia)

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 radiologicalissues 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 ofdesign, use of equipment, maintenance, operational and administrative controls in place.
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 theocean.

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 withthe limits imposed by the regulator and to fulfill the duty to protect members of the public. A
program of 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 theenvironment. Radioactivity discharge limits are set for liquid effluent to meet the WHO
Guidelines for Drinking Water Quality (2011) for radioactive species at the point of thereceiving sewage treatment plant (Cronulla). Waste water is analysed for gross alpha and beta
radioactivity concentration and must comply with the derived limits (based on a dilution factorof 25 prior to the sewage plant) before it is released. Annual sampling at the sewage treatment
plant and outfall has always shown that the levels of radioactivity detected are below those set
in the WHO guidelines. The information collected from environmental monitoring is publishedannually 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
and response in the event of a radiation emergency. The five main components to the emergency
planning arrangements include:Response plansStanding Operating Procedures (SOPs)



Communication and consultation



Testing and review

Emergency response training

The response plan was developed by ANSTO and the ANSTO Local Liaison Working Party(LLWP) in accordance with the State Emergency and Rescue Management Act.

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FNCA Consolidated Report on Radiation Safety (Australia)

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 and to
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:

NSW State Disaster Plan (DISPLAN)

NSW State Lucas Heights Emergency Sub-Plan

NSW State CBRN Hazardous Materials Emergency Sub-Plan

NSW Sydney Metropolitan Emergency Management District Disaster Plan (DistrictDISPLAN)

Sutherland Shire Local Disaster Plan (Local DISPLAN)



OPAL Reactor Facility Emergency Plan

In such an event ANSTO would continue to provide technical advice and assistance to the
NSW authorities that would be in control.
2.3 Safe Management of Radioactive Waste
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) are produced in Australia by the mining, mineral sands processing and otherresources 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 Table7.

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FNCA Consolidated Report on Radiation Safety (Australia)

Table 7: Radioactive Waste Management Facilities

Location

Main Purpose

Essential Features and estimated waste
inventory

ANSTO, Lucas
Heights, NSW

Treatment and Packaging

ANSTO Lucas
Heights, NSW

Storage

Mt Walton East
Intractable Waste
Facility, WA
Woomera Protected
Area, SA
Woomera Protected
Area, SAEsk Storage Facility,
Qld

DisposalManagement of waste from research reactor
operation, radiopharmaceutical production,
research and development
1844 m3 low level waste
441 m3 intermediate level waste
Near surface disposal of low level radioactive
waste generated in the State of Western Australia

OthersStorage

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 Radioactive Waste
Management Facility (NRWMF) 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.
It is internationally accepted that centralised radioactive waste management facilities offer
substantial safety and security benefits by minimising risk of accidental loss of control ofradioactive waste, thereby protecting the community and environment from any adverse effects.
In 2012, the Australian Government introduced the National Radioactive Waste Management Act
2012. The Act establishes a legislative framework for siting a facility for managing radioactive
waste arising from medical, industrial and research uses of radioactive material at a single site on
volunteered land. Currently Australia’s radioactive waste is stored at more than 100 less thanideal sites around Australia. This approach will promote the consistent, 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 Safety of Radioactive
Waste Management. Two volunteer nomination processes are provided for by the Act. The firstallows for a Land Council in the Northern Territory to volunteer Aboriginal land on behalf of its
Traditional Owners. If, for any reason, a facility cannot be sited on Aboriginal land nominated bya Land Council in the Northern Territory, a nation-wide volunteer process for siting a facility will
be initiated. Under both processes, extensive consultation will be undertaken. The Act will also
ensure that the selected site undergoes full environmental, heritage and other approval processes.
2.3.1 Radiation Safety in the Management of Radioactive Waste
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 the19

FNCA Consolidated Report on Radiation Safety (Australia)classification of radioactive wastes based on their physical form, chemical nature andradioactivity. These waste classifications provide guidance as to what radiation safety measures
are required for both processing and storage.
In April 2010, ARPANSA issued a Safety Guide on the Classification of Radioactive (RPS20) waste to be adopted nationally in order to standardise the classification of radioactive wastewith reference 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 for radiation protection purposes. Exemption activity concentrations and exempt
activities of each radionuclides are listed in the Schedule 4 of the National Directory for
Radiation Protection (RPS 6) which is readily available on ARPANSA’s website.
 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 to arrangements approved by the relevant regulatory authority, foruncontrolled disposal, use or discharge. This class includes waste containing primarily
radionuclides with very short half-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 a moderate level of containment and isolation and therefore is suitable for disposal
in a near surface, industrial or commercial, landfill type facility with limited regulatory
control. Such landfill type facilities may also contain other hazardous waste. Typicalwaste in this class includes 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 of long lived radionuclides. Such waste requires robust isolation andcontainment for periods of up to a few hundred years and is suitable for disposal inengineered 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 thatprovided by near surface disposal. However, ILW needs little or no provision for heatdissipation during its storage and disposal. Intermediate level waste may contain long
lived radionuclides, in particular alpha emitting radionuclides, which will not decay toan activity concentration acceptable for near surface disposal during the time for which
institutional controls can be relied upon. Therefore waste in this class requires disposal
at greater depths, in the order of tens of metres to a few hundred metres.
 High level waste (HLW): Waste with activity concentration levels high enough togenerate significant quantities of heat by the radioactive decay process or waste withlarge amounts of long lived radionuclides that need to be considered in the design of adisposal facility for such waste. Disposal in deep, stable geological formations usually20

FNCA Consolidated Report on Radiation Safety (Australia)

several hundred metres or more below the surface is the generally recognised option for
disposal of HLW.
In 2010 ARPANSA also issued a technical report (TR-152) titled the Classification and
Disposal of Radioactive Waste in Australia – Consideration of Criteria for Near Surface Burial
in an Arid Area. This report provides guidance on the selection of sites for near-surface disposalof waste and describes procedures for the development of qualitative and quantitative criteria
for the three disposal categories of waste, Category A, Category B and Category C.
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 National Radioactive Waste
Management Facility), the above definition does not apply and all wastes are to be reclassified
and managed in accordance with ARPANSA’s RPS 20 Safety Guide for Classification ofRadioactive Waste.
2.3.2 Radiological Protection for Radiation Workers
ANSTO personnel involved in the management of radioactive waste are classified asradiation workers and are protected according to the radiation protection management system
and measures described in sections 2.2.1 and 2.2.2. All other personnel involved in the
management of radioactive waste within Australia are to adhere to the relevant radiation safety
regulations within their jurisdiction. The radiation safety management principles and radiation
protection measures would generally be in line with ARPANSA’s Radiation Protection
Standards and Codes (see sections 2.1.1 and 2.1.2).
2.3.3 Radiological Protection for Radiation Area
The radioactive waste management facilities at ANSTO apply radiation protection andcontamination control measures in harmony with the rest of the organisation as described in
section 2.2.3. Other radioactive waste management operators and facilities within Australia
apply radiation protection and contamination controls in accordance with their jurisdictional
regulations, which would largely accord with the measures specified in ARPANSA’s Radiation
Standards and Codes.
2.3.4 Radiological Protection for the PublicRadioactive waste management controls and the control of radioactive discharges are inplace in all jurisdictions to current international standards as required by the relevant regulator.
ARPANSA’s Radiation Protection Standards and Codes provide guidance on all management
aspects of radioactive waste (exposure limits, classification, transport, NORM, radioactive
waste in mining, radioactive source security predisposal management) to ensure appropriate
measures are in place for the radiological protection of the public.

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FNCA Consolidated Report on Radiation Safety (Australia)

2.3.5 Radiation Emergency Preparedness
For emergency preparedness in relation to radioactive waste management at ANSTO see
section 2.2.5. For emergency preparedness in relation to radioactive waste management at otherfacilities see section 2.1.5.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

2. Bangladesh
Part 1. Radiation Safety in RI Facilities.............................................................................................. 24
1.1. General ................................................................................................................ 24
1.1.1 Legislative and Statutory Framework................................................................................ 24
1.1.2 Legal Background .............................................................................................................. 24
1.2 Outline of Radiation Facilities and Radiation Sources .................................... 26
1.2.1 Number of Specialists and Workers in Related Organizations and Radiation Facilities including
Related Facilities ......................................................................................................................... 26
1.2.2 Activity and Number of Radiation Sources and Generators ............................................. 26
1.3 Education and Training ...................................................................................... 27
1.3.1 RI Usage:......................................................................................................................... 28
1.3.2 Radiological Protection...................................................................................................... 28
1.4 Standardization on Radiation and Radioactivity.............................................. 29
Part 2. Status of Radiation Safety Management ................................................................................. 29
2.1 Radiation Safety Management in various RI Usage ........................................ 29
2.1.1 Radiation Protection Programme....................................................................................... 29
2.1.2 Radiation Emergency Preparedness .................................................................................. 30
2.2 Radiation Safety Management in Research Reactors ...................................... 30
2.2.1 Radiological Protection for Radiation Worker, Radiation Area, and Public..................... 31
2.2.2 Radiation Emergency Preparedness .................................................................................. 33
2.3 Radiation Safety Management in Nuclear Power Plants ................................ 33
2.4 Radiation Safety Management in Radioactive Waste Management ............... 33

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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 defense 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), now called Bangladesh Atomic Energy
Regulatory Authority (BAERA) is responsible for the regulation of issues related to accounting
and control of nuclear materials, radioactive substances and physical protection. The BAERA isthe competent authority for licensing shipments out of Bangladesh and giving consent toshipments into Bangladesh.
The basic legal and statutory framework for Nuclear Safety and Radiation Control is inplace. A draft Nuclear Safety Law has been submitted to the Agency for comments and it iscurrently 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 radiologicalprotection, although the regulations of public exposure is presently covered by anexisting NSRC Rule-97.
1.1.2 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
the Government of Bangladesh. This act will establish the set up basic requirements for
management of radioactive waste; define basic requirements, licensing procedures andresponsibilities of different organizations involved in nuclear activities and related radioactive
waste management.

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FNCA Consolidated Report on Radiation Safety (Bangladesh) 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) presently known as
BAERA have prepared new rules for the ‘Radioactive Waste and Spent Fuel Management – 2008,
which is currently under the Agency’s review.
Present Status:
A new act, called ‘Bangladesh Atomic Energy Regulatory (BAER) Act-2012’, has been
passed 29 March 2012 by the parliament. As per act there is provision to establish an
independent Regulatory Authority under the Ministry of Science and Technology to perform
its regulatory activities. New Act will empower the regulatory authority to develop safety
principles and criteria. The New Act and NSRC Rules-1997 include exclusion, exemption andclearance criteria. The new act allows appeal against regulatory decisions. Under the proposed
act, a five-member regulatory body, titled ‘Bangladesh Atomic Energy Regulatory Authority’
headed by a chairman, will be constituted to supervise the activities of the operator of Rooppur
Nuclear Power Plant to be constructed with the assistance of Russian Federation. Besides, anadvisory committee will be formed with experts from related sectors. The issues of definition,
goals and activities of the authority, determination of compensation, security and safety of thepower plants as well as safety measures against radiation and management of nuclear waste
have been mentioned in the proposed act.

Figure 1: Present Structure of Bangladesh Atomic Energy Regulatory Authority (BAERA)

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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 ofRadiation Facilities
Numbers (Installation/unit)
specialist/worker
Diagnostic X-ray units
4200
5500
Research Reactor

1

20

Dental X-rays

190

380

Nuclear medicine departments

18

122

Radiotherapy facilities

14

100

Teletherapy

9100

Brachytherapy

725

Industrial radiography facilities

14-

Industrial or research irradiators

3

16

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

12

109

Linear Accelerator

920

1.2.2 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. NoSourceActivity

Units

01

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.
Short duration 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 andTechnology (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.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

The training programme for the radiation protection and management are provided by the
BAERA for the Radiation Control Officers (RCO’s), radiation protection management staff andother facility personnel. In order to formulate training and education policies that are involved theapplication of the nuclear science and technology, BAEC has recently established a training
institute in AERE, Savar for the scientists and engineers.

Figure 2: Training Institute at AERE Savar

1.3.1 RI Usage:
 Production of radioisotopes: (e.g.99mTc,131I ) Agriculture: 65Zn, 32P, 54Mn, 3H, 35S and 14C
152
 Research:137Cs,60Co,226Ra,241Am,131I,90Sr,22Na,192Ir,
Eu etc.
192
137
 Industrial Radiography practices:
Ir, Cs137
 Nuclear Well-logging Practices: Am-Be,
Cs, 232Th, 226Ra, 60Co
241
 Nucleonic Gauge Practices:
Am 60Co, 137Cs, 90Sr, 85 Kr, Am-Be, 55 Fe, 63 Ni
125 131 99m
 Nuclear Medicine Facility:
I, I, Tc, 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 machinesfrom the Ministry of Health and Family Welfare to the BAEC. The regulatory function is
exercised by the Bangladesh Atomic Energy Regulatory Authority (BAERA) which is a separate
body now. 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 or potential exposure are responsible for the protection of the employees fromoccupational exposure. The provision of individual monitoring services is mandatory. A national
system (logistics and/or technical capabilities) for monitoring the levels of radioactivity infoodstuffs and selected commodities before they are traded exists.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

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 tothe improved accuracy and reliability on radiation and radioactivity measurement.

Figure 3: Secondary Standard Dosimetry Laboratory at AERE, BAECPart 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 therelated 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

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

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

Dose limits

Effective dose

Occupational workers
20 mSv per averaged over
five consecutive years
50 mSv in any single year

Annual equivalent dose to
The lens of the eye
The skin
The extremities

150 mSv
500 mSv
500 mSv

Effective dose

General public
1 mSv in a year
5 mSv in any single year, in
special circumstances, provided
that the average dose over fiveconsecutive years does notexceed 1 mSv/yr.
15 mSv
50 mSv
50 mSv

2.1.2 Radiation Emergency Preparedness
The Nuclear Safety and Radiation Control Division (NSRCD) now called BAERA incooperation with BAEC’s Health physics and radiation-monitoring laboratories has been
assigned to provide expertise and services in radiation protection. Capabilities for regulartraining of emergency personnel are being developed under national emergency plan. However,some capabilities have already been developed 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 local subcommittee have been formed to perform responsibilities
during radiological emergency.
Recently an act named Bangladesh Atomic Energy Regulatory (BAER) Act-2012 has been
passed in the National Parliament of Bangladesh. A nuclear or radiological emergency
preparedness and response related separate Chapter (Chapter-VI) has been incorporated in thisAct. According to the new Act, Bangladesh Atomic Energy Regulatory Authority (BAERA) is
responsible for coordinating the preparation of the national emergency plan regarding nuclear
and 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.

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FNCA Consolidated Report on Radiation Safety (Bangladesh)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 aquarterly 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 andsafety provisions are not normally 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)

Table 7:

Location of radiation control and supervised area at TRF

Location

Designated Areas

Reactor top

Controlled area

Reactor Hall

Controlled area

Control room

Supervised area

Public gallery

Supervised area

Reactor Manager Office

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

Supervised area

Neutron spectrometer lab

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

Controlled area

Radioactive waste storage room

Controlled area

Heat exchanger room (groundfloor)

Supervised area

Primary pump & decay tank room

Supervised area

Stack (Ground floor)

Supervised areast

Stack (1 floor)

Supervised areandfloor)

Supervised areardfloor)

Supervised area

Stack (2Stack (3Figure 4:

3 MW TRIGA Mark II Research Reactor at AERE, Savar

32

FNCA Consolidated Report on Radiation Safety (Bangladesh)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 and procedures, taking part in the emergency exercises and publishing the appropriate
information. As a result of the feedback of the experiences gained during the exercises, theemergency plans are being reviewed and improved. A complete organizational infrastructure ofradiation 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 andother nuclear researches. These wastes are classified into low level radioactive waste andintermediate level radioactive waste. Criteria used to define and categorize radioactive
wastes bases on the classification system as recommended by the IAEA. All radioactive
wastes, including disused sealed sources, are kept to a minimum, adequately processed,
stored or disposed of under regulatory 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 asreasonably achievable (ALARA). The radiation exposure of site personnel and membersof the public conforms to the requirements 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 for :a) Appropriate control of radiation doses to persons resulting from the operation.
b) Appropriate control of the amounts of radioactive substances released to theenvironment 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 take account of the design provision for:a) Restricting the exposure of site personnel and of the general public within,established limits 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

33

FNCA Consolidated Report on Radiation Safety (Bangladesh)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 theexposure control measures within their area of activity, which are specified in theradiation protection programme. Consequently, particular emphasis is given to all facility
personnel to ensure that they are fully aware of both the radiological hazards and theprotective measures available. Special attention is given to the fact that, personnel at thefacility 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 the radiation protection programme is being implemented and that its objectives areachieved, and undertakes corrective action if necessary.
If reference level is exceeded, the operating organization investigates the matter forthe 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 bodydesignated by the national regulations.
If the limits for either personnel exposure or radioactive release are exceeded, theregulatory body and/or relevant authority informs in accordance with the requirements.
The radiation protection programme provide for the medical surveillance, thepersonnel who may be occupationally exposed to significant radiation doses. The legal
dose limits for both occupationally exposed personnel and the general public aredescribed in the table below:
Table 8:

Effective dose and annual dose limit for occupational worker and general public

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

34

FNCA Consolidated Report on Radiation Safety (Bangladesh) 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 and a whole body counter provide an individual
radiation measurement for the facility personnel. Gamma spectrometry and radiation
detectors system are also available in this unit for determination of the presence andquantity of radioactivity.

Figure 5: Individual Radiation Exposure Control

 Area Monitoring
For administrative purposes, disposal to the environment during routine operation islimited to clearance level for all radioisotopes. It is the policy of Central Radioactive
Waste Processing and Storage Facility (CWPSF) operation group does not to releaseradioactive material above naturally existing amounts to any stream or ground water
under normal operation conditions. The content of radioactivity in the treated wastes ischecked to determine the concentration of radioactivity.
The solid wastes are collected and located on controlled area of the CWPSF foraccumulation of clean and low - level contaminated waste.
Air sampling of site are taken weekly by health physics staff and the results arerecorded. 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 invarious parts of operation area. Each detector has a Geiger Muller detector as radiation
sensor. The following is a list of equipment available area monitoring:a. Portable survey meters
b. Portable air sampler
c. Geiger Muller Counterd. Portable gamma analysis
e. Portable Dose - rate meter

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FNCA Consolidated Report on Radiation Safety (Bangladesh)

Figure 6: Radiation survey meters used for the measurement of dose rate

 Environmental Monitoring
Air samples are collected and analysed in several locations within CWPSF, AERE
and evaluation of radioactivity in these samples is done in regular basis. Backgroundradioactivity around the setting locations of CWPSF, AERE are measured and evaluatedevery month.

Figure 7: Environmental Radioactivity Monitoring Emergency Preparedness
The operating organization is developing the capabilities for protection of the public
and the environment by establishing policies, strategies and programme involving
radiation exposure and radiological consequences due to accident conditions.
Bangladesh Atomic Energy Regulatory Authority (BAERA) in cooperation with
BAEC's relevant laboratories is presently dealing radiation emergency situations. There
are adequate arrangements for radiation workers and staff to be aware of the medical
symptoms of radiation exposure and notification procedures. Regular basis trainings arebeing conducted in order to make the facility personnel and public aware of radiation andradiological emergency.

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FNCA Consolidated Report on Radiation Safety (China)

3. China
Part 1. Radiation Safety in RI Facilities .............................................................................................. 38
1.1 General .................................................................................................................................. 38
1.1.1 Legislative and Regulatory Framework ............................................................................ 38
1.1.2 Regulatory Body ................................................................................................................ 38
1.2 Outline of Radiation Facilities and Radiation Sources......................................................... 40
1.2.1 Authorization ...................................................................................................................... 40
1.2.2 Workers and Specialists in Radiation Facilities................................................................. 40
1.2.2.1 Radiation Workers ........................................................................................................... 40
1.2.2.2 Radiation Protection Supervisors.................................................................................... 40
1.2.2.3 Activity of Radiation Sources and Number of Generators............................................. 40
1.2.3 Recent Movement Concerning Radioisotope Sources ...................................................... 41
1.2.3.1 Develop Conditioning Capability for Spent Radioactive Source .................................. 41
1.2.3.2 Promote Disposal of LILW ............................................................................................. 41
1.2.3.3 Promote Minimization of Radioactive Waste................................................................. 41
1. 4 Education and Training ........................................................................................................ 41
1.4.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc. ........ 41
1.4.2 The Nuclear Reactor and Fuel Law ................................................................................... 42
1.4.3 Examples of Education and Training................................................................................. 42
1.5 Standardization on Radiation and Radioactivity .................................................................. 43
Part 2. Status of Radiation Safety Management ................................................................................. 44
2.1 Radiation Safety Control in RI facilities............................................................................... 44
2.1.1 Radiation Safety Control System....................................................................................... 44
2.1.2 Radiation Protection of Workers ........................................................................................ 44
2.1.3 Radiation Protection of Working Area............................................................................... 45
2.1.4 Public Radiation Protection ............................................................................................... 45
2.1.5 Emergency Action .............................................................................................................. 46
2.2 Radiation Safety Management in Nuclear Facility .............................................................. 46
2.2.1 Radiation Safety Management System.............................................................................. 46
2.2.2 Radiological Protection for Radiation Worker .................................................................. 47
2.2.3 Radiation Area Management ............................................................................................. 48
2.2.4 Radiation Protection for Public .......................................................................................... 49
2.2.5 Nuclear Emergency Response ........................................................................................... 50

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FNCA Consolidated Report on Radiation Safety (China)

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 thedevelopment 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 andcontrol of Radioactive Pollution, through review and authorization, supervision and inspection,and supervisory monitoring of the activities associated with license holders. Thus it can beensured that the license holders assume the responsibility of safety and conduct activities incompliance with relevant laws and regulations. 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 and publication 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, incooperating with other relevant organizations in providing guidance on, and supervisionof the preparation and implementation of NPP emergency plan, and working with other38

FNCA Consolidated Report on Radiation Safety (China)

relevant organization in participating with nuclear accident emergency through theconciliation 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 thecase of nuclear and radiation accident.
 Ministry of Public Security
The Ministry of Public Security is principally responsible for investigating and recovering
the lost 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
in China;
2) To research and establish developing program, planning, and nuclear industry standard
for peaceful 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 ofsurveillance and coordination 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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FNCA Consolidated Report on Radiation Safety (China)

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
category sources, MEP(NNSA) takes direct responsibilities of reviewing, approving andgranting licenses. Authorities concerned at provincial level grant licenses for the rest ofradioactive 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 tocorrectly define, according to an incomplete statistics, 300 thousand people are engaging in theutilization of 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 andDalian, 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 and Radiation Safety Center as technical support and guarantee for itself.
An expert panel concerning nuclear safety and the environment was set up to provide technicalsupport in aspects of drafting nuclear safety and radiation safety laws and regulations,decision-making, technical development, technical review 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 ofexperiences in nuclear(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 of40

FNCA Consolidated Report on Radiation Safety (China)

economy, in particular 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 numberof the producers, vendors and users of radioisotopes amount to about 13051 across the country,with more than 140,000 of sealed sources involved in total.
1.2.3 Recent Movement Concerning Radioisotope Sources
1.2.3.1 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
for the 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.
1.2.3.2 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 acomprehensive manner and direct the development trend of solid LILW disposal and promote
the development of regional disposal site for LILW.
1.2.3.3 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 moreaction in controlling generation of waste, upgrading management, introducing advanced waste
reduction technology, promoting specialization and socialization in radioactive waste treatment
service.
1. 4 Education and Training
1.4.1 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 ofthem. 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 to41

FNCA Consolidated Report on Radiation Safety (China)

have an enhanced training management and consistent training and examination requirements.
Training organizations have been accredited with whole process supervision being provided oftraining and examination.
1.4.2 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.
1.4.3 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 of Radioactive Pollution to enhance the management of the key posts with nuclear safety
related responsibility, ensure nuclear and radiation environmental safety, and maintain national andthe 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
the given examination. The validity period of a registration is 2 years. Continued educational regime
is performed for the registered nuclear safety engineers.

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FNCA Consolidated Report on Radiation Safety (China)

The occupational scope of a registered nuclear safety engineer covers review of nuclear safetycase, 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) .
1.5 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 publichazards. 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 theRegulations on Safety and Protection of Radioisotope and Ray-generating Installations, statingthat licensing system shall be applied to the production, distribution and use of radioactive
sources and the recovery and storage of disused radioactive sources. Various administrative
departments under the State 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 StateCouncil 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 toradioactive waste disposal. In 1993, the State 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 ofChina on Prevention and Control of Radioactive Pollution was promulgated for enforcement. It
defines that the environmental protection competent authority under the State Council has theoverall responsibilities for the country-wide prevention and control of radioactive pollution by
virtue of the relevant national laws and that other administrative departments under the StateCouncil 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 tobe revised, and renamed Regulations on Safety and Protection of Radioisotope andRay-generating Installations. It lays out that the previous by-stage, multi-sector regulatory
approach was changed to a unified regulatory system by the environmental protection competentauthority of radioactive sources. In 2002, the Basic Standards for Protection against Ionizing
Radiation and for the Safety of Radiation Sources (GB18871-2002), a Chinese Standards, wasissued.

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FNCA Consolidated Report on Radiation Safety (China)

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 and radioactive Sources(Chinese Standards GB18871-2002), have constructed aspectrum 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
and monitoring of foresaid systems, construction of information system for monitoring andcontrolling radioactive sources, management of training radiation workers and monitoringdose information to persons exposed to radiation, response to emergencies, and inspection ofradiation 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 theirjurisdiction.
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 file44

FNCA Consolidated Report on Radiation Safety (China)

personal 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, theradiation protection facilities, necessary safety interlock and alarming devices should be set
up at the entrance. Safety measures to prevent mis-operating and unexpected radiation exposurefor the employee or the public should be taken.
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 mostappropriate measurement methods and procedures; iiii) reference level and the actions to betaken if they are exceeded.
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,
and the limitation of normal exposure of the relevant critical group, which is attributableto such 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 protectionof 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 ;45

FNCA Consolidated Report on Radiation Safety (China)

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 investigationand classification of the accident. For this reason, Radiation Accident Emergency Plan is
specially established. Under the Council of State Decree 449, the environmental protection
agencies of the people’s governments at or above county-level should work with the agencies
responsible for public security, health and finance at the same level to make joint effort toprepare radiation accident emergency plan within their own administrative areas. The plan issubject to approval of county-level people’s governments to ensure their legality and validity
and should make them available 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 theeffectiveness of the 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 theenvironment, health and public security. After receiving such a report, the agencies should
dispatch personnel to the accident site to conduct emergency fieldwork in a way consistent withthe provisions, and at the same time report the information to their respective upper levelcompetent agencies in a prescribed way. The personnel that have arrived at the accident siteshould 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 radiological accident, the people’s governments at the level ofprovince, autonomous region and municipality directly under the State shall report to the StateCouncil 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
the achievement 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
and Control 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;46

FNCA Consolidated Report on Radiation Safety (China)

2) The operator of any nuclear facility shall monitor the types and concentrations ofradionuclides in the surrounding environment and the quantity of radionuclides in effluentsfrom such a facility, and report the monitoring results to the competent authorities ofenvironmental 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 tothe competent authorities of environmental protection.
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
to radioactive 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 overdefined 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 asingle 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 instandards, as shown in the following Table 1.

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FNCA Consolidated Report on Radiation Safety (China)

Table 1: Monitoring results of occupational exposures

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

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 accountbeing 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 andoccupancy 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
their goal achievement, and if necessary taking necessary corrective actions; and48

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 andreduce 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 arelocated. 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 witha view to carrying out environmental radioactivity monitoring to ensure compliance with theprovision of the relevant national laws and regulations, satisfaction with radioactive waste discharge
limits and protection of the public from radiation impacts arising from nuclear facility operation.
Environmental radioactive monitoring data shall be used to assess and analyze the validity ofcontrolling radioactive material release into the environment, the public exposure from nuclear
facility’ effluent, long term trend in variation in environmental radioactivity, migration and dispersionof radioactive material in the environmental media and the reality of environmental model used forestablishing 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 radiationlevel is investigated within 50 km of the proposed sites with others within 20 km of the proposed sites.

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FNCA Consolidated Report on Radiation Safety (China)

What to be analyzed and measured includes environmental radiation level and radionuclides released
from nuclear facilities. Before operation of NPPs in China, environmental radioactivity backgrounds
are measured and the results preserved in such a manner as to ensure the representative ofenvironmental 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 whatis deemed 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 ofradioactive 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
typical selected 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 NPPsprior to their operation, where derived intervention levels are provided for in order to assessmonitoring 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, withregular test and calibration. 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 andother environmental media, to assess the dose equivalent to the public and environmental impact
arising from the 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
the surrounding 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

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FNCA Consolidated Report on Radiation Safety (China)

arrangements, and overseeing the development and implementation of NPP nuclear accident
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
and making 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 plantboundary. 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
or plant 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 the51

FNCA Consolidated Report on Radiation Safety (China)

plant area, 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 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 1. Status of Radiation Safety Management ..........................................................................54
1.1 Radiation safety management in Radioactive Waste Management ..............................54
1.1.1 Radiation Safety Management System.......................................................................54
1.1.2 Radiation Safety Survrilliance ....................................................................................54
1.1.2.1 Area Monitoring .......................................................................................................54
1.1.2.2 Personnel Monitoring...............................................................................................55
1.1.2.3 Effluent Monitoring .................................................................................................55
1.1.2.4 Monitoring Public Exposure ....................................................................................55
1.1.2.5 Environmental Monitoring ......................................................................................55
1.1.2.6 Emergency Preparedness .........................................................................................55

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FNCA Consolidated Report on Radiation Safety (Indonesia)

4. Indonesia
Part 1. Status of Radiation Safety Management
1.1 Radiation safety management in Radioactive Waste Management
1.1.1 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 arecompacted 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 fromgenerating 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.
1.1.2 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.
1.1.2.1 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 isprovided for equipments 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 installed at few locations in the facilities. A routine air sampling programme is inplace, employing discontinuously operated air samplers at fixed location, and by batch air
samplers during routine and specific operations.

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FNCA Consolidated Report on Radiation Safety (Indonesia)

1.1.2.2 Personnel Monitoring
Personnel monitoring for external exposure is routinely carried out using thermo
luminescent dosimeters (TLD). In addition, digital personnel dosimeters are used for
immediate assessment of radiation 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 expected contaminated, has revealed no occurences of internal contamination in2009 at Serpong.
1.1.2.3 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 withthe appropriate environmental radioactivity level standards. Environmental monitoring carriedout every 3 months on Cisadane river. Analysis results of effluent samples has revealed that60
Co and 65Zn in the liquid effluent. Most of the effluent is generated by the Serpong Research
Reactor.
1.1.2.4 Monitoring Public Exposure
Surface water from Cisadane river and other environmental components are regularly
monitored for their radioactivity concentration. Estimated maximum possible radiation
exposure of 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 inradiation dose in the environment, only the background radiation dose from terrestrial exposureand cosmic ray.
1.1.2.5 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 inradiation field is investigated for its causes, and corrective actions taken. Samples of groundwater and surface soil from around RWMTC are collected with a defined periodicity andanalyzed for radionuclide quantification.
1.1.2.6 Emergency Preparedness
RWMTC is part of the Serpong Nuclear Area Emergency Preparedness and Response
Arrangements, so that the emergency preparedness refers to emergency preparedness
programmes of Serpong Nuclear Area.

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FNCA Consolidated Report on Radiation Safety (Japan)

5. JapanPart 1. Radiation Safety in RI Facilities.............................................................................................. 57
1.1 General ................................................................................................................. 57
1.1.1 Legislative and Regulatory Framework ............................................................................ 57
1.2 Regulatory Body .................................................................................................. 57
1.3 Outline of Radiation Facilities and Radiation Sources .................................... 60
1.3.1 Authorization ...................................................................................................................... 60
1.3.2 Workers and Specialists in Radiation Facilities................................................................. 62
1.3.4 Recent Movement Concerning Radioisotope Sources...................................................... 66
1.4 Education and Training ...................................................................................... 66
1.4.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc......... 66
1.4.2 The Nuclear Reactor and Fuel Law ................................................................................... 67
1.4.3 The Labor Standards Law .................................................................................................. 67
1.4.4 Examples of Education and Training ................................................................................ 67
1.5 Standardization on Radiation and Radioactivity.............................................. 68
Part 2. Status of Radiation Safety Management ................................................................................. 70
2.1 Radiation Safety Control in RI facilities............................................................ 70
2.1.1 Radiation Safety Control System....................................................................................... 70
2.1.2 Radiation Protection of Worker ......................................................................................... 72
2.1.3 Radiation Protection at Work Area .................................................................................... 73
2.1.4 Radiation Protection of the Public ..................................................................................... 73
2.1.5 Radiation Emergency Response ........................................................................................ 74
2.2 Radiation safety management in Research Reactors ....................................... 76
2.2.1 Radiation Safety Management System.............................................................................. 76
2.2.2 Radiation Protection for Radiation Worker ....................................................................... 76
2.2.3 Radiological Protection for Radiation Area....................................................................... 77
2.2.4 Radiological Protection for the Public............................................................................... 78
2.2.5 Radiation Emergency Preparedness .................................................................................. 78
2. 3 Radiation Management in Nuclear Power Plants ........................................... 78
2.3.1 Radiation Safety Management System.............................................................................. 78
2.3.2 Radiological Protection for Radiation Worker .................................................................. 79
2.3.3 Radiation Area Management ............................................................................................. 80
2.3.4 Radiological Protection for the Public............................................................................... 81
2.3.5 Radiological Emergency Response ................................................................................... 84
2.4 Radiation Safety Control at the Radioactive Waste Treatment Facility ......... 86
2.4.1 Radiation Safety Management System, Radiological Protection for Radiation
Worker, and Radiological Protection for Radiation Area ........................................................... 86
2.4.2 Radioactive Waste Management in the Research Facilities.............................................. 92
2.4.3 Radioisotope Waste Management Generated from the Use of Radioisotope
and Radiation............................................................................................................................... 93

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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 futureenergy resources, achieve progress in science and technology, and promote industry byencouraging research, development and utilization of nuclear energy, and thereby contribute to
the improvement of the welfare of human society and the national living standard.” The basic
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, andperformed on a self-disciplined basis under democratic administration, and the results thereof
shall be made public and actively contribute to international cooperation.” The law wasreformed on 27th June 2012 according to experiences and lessons learned from the accident at
Fukushima Dai-ichi Nuclear Power Station (NPS) of TEPCO due to the Tohoku District-off the
Pacific Ocean Earthquake and the resulting tsunamis.
In order to attain these objectives and achieve the basic policy, the law prescribes thefollowing:- Establishment of the Nuclear Regulation Authority (NRA) as an external organization of
the Ministry of the Environment (MOE) and the Nuclear Emergency Preparedness
Commission (NEPC) under the Cabinet- Establishment of the Atomic Energy Commission (AEC) and its 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 “Law for the Regulation of Nuclear Source Material”, Nuclear Fuel
Material and Reactors (Reactor Regulation Law)”, “Electricity Utilities Industry Law”, “Law
Concerning Prevention of 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,” “Special Law of Nuclear Emergency Preparedness (Special Law for
Nuclear Emergency),” “Law for Technical Standards of Radiation Hazards Prevention” and“Specified Radioactive Waste Final Disposal Act” etc.
1.2 Regulatory Body
The mandate of the regulatory bodies is to ensure public safety through securing the safety of
the nuclear facilities. Their obligations are to implement the above-described legislative andregulatory framework. The regulatory bodies are responsible for conducting regulatory activities

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prescribed in the Reactor Regulation Law, the Radiation Hazards Prevention Law, etc. on thebasis 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 thenational budget.
Until Sep. 18, 2012, the Ministry of Economy Trade and Industry (METI) had served as thecompetent ministry for safety regulation on activities concerning utilization of nuclear energy,
and the Nuclear and Industrial Safety Agency (NISA) had administered the regulatory activities
as a special organization for METI.
Until Apr. 1, 2013, the Ministry of Education, Culture, Sports, Science and Technology(MEXT) had served as the competent ministry for the safety regulation over the nuclear
utilization associated with science and technology and the utilization of radioisotopes (except
medicines), and the Science and Technology Policy Bureau (STPB) had administered its
regulatory activities. The Ministry of Health, Labor and Welfare (MHLW) had governed thesafety regulation concerning medical facilities as the competent ministry, and the Pharmaceuticaland Food Safety Bureau (PFSB) and the Health Policy Bureau (HPB) administering its
regulatory activities.
Table 1: Regulatory bodies and Assigned Facilities and Activities up until Sep. 18, 2012.

Regulatory bodyNISA (Nuclear and Industrial
Safety Agency)

METI (Minister of Economy

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

Trade and Industry)

STPB (Science and Technology
Policy Bureau),

MEXT (Ministry of Education,
Culture, Sports, Science andTechnology)

HPB (Health Policy Bureau)
PFSB (Pharmaceutical andFood Safety Bureau)

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.

MHLW (Ministry of Health,
Labor and Welfare)

These regulatory bodies had clearly defined duties on safety regulation, and their
independence is ensured both in legislation and in substance.
Until Sep. 18, 2012, the Nuclear Safety Commission (NSC), consisting of members whom
the Prime Minister had appointed with consent of the diet, observed and audited activities ofthese regulatory bodies in a Regulatory Review. The NSC established the basic policy for safety
regulations to maintain the consistency among the regulations. The consistency of the technicalstandards for prevention of radiation hazard was discussed at the Radiation Review Council
under the MEXT until Apr. 1, 2013.
On Sep. 19 2012, the NRA was newly established as an external organization of the MOE toresolve the problem caused by having both the “promotion of utilization” and “safety58

FNCA Consolidated Report on Radiation Safety (Japan)

regulations” under the same organization. The safety regulation division was separated fromMETI since NISA, which was responsible for nuclear safety “Regulations,” had been placed
under the auspices of the METI, tasked with promoting the utilization of nuclear power.
The affairs for nuclear power regulations assumed by each related government agency andthe affairs for protecting nuclear material and the like（nuclear security） have been unified into
the NRA. Furthermore, the NSC of Japan was abolished and the necessary functions have been
integrated into the NRA. On Apr. 1, 2013, the regulations, such as for the nuclear
nonproliferation safeguards*, radiation monitoring and the use of radioisotopes, which had been
the responsibility of the MEXT were also transferred and the “regulation” related functions havebeen centralized under the responsibility of the NRA.

Figure 1: Change of Regulatory System

The current relationship between regulatory bodies and assigned facilities and activities isshown by the following table.
Table 2: Regulatory bodies and Assigned Facilities and Activities after Apr. 1, 2013

Regulatory body
NRA (Nuclear Regulation
Authority)

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.

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FNCA Consolidated Report on Radiation Safety (Japan)

Reference: Government of Japan, Joint Convention on the Safety of Spent Fuel Management and on the Safety ofRadioactive Waste Management, National Report of Japan for the Second Review Meeting Oct. 2005.
 Nuclear Regulation Authority, Japan- Nuclear Regulation for People and the Environment, Pamphletof Nuclear Regulation Authority.

1.3 Outline of Radiation Facilities and Radiation Sources
Laws and Ordinances apply uniformly regardless of the category of the organization. It isappropriate to think of them as stipulating the minimum standards that the organizations and theradiation workers should observe, and each organization, while of course meeting the legallyprescribed standards, should implement radiation control appropriate for its own activities.
The Law Concerning Prevention of Radiation Hazards was drafted and modified in line withrecommendations 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 in the use of radiation
or radioisotopes. In order to attain this purpose, the Law provides for the regulation of facilities
and for the regulation of people’s actions, etc. (requirements for facilities and actions).
1.3.1 Authorization
Permission by or notification to the Nuclear Regulation Authority (NRA) is required for theuse of radioisotope sources and radiation generators.
(1) Permission: The use of unsealed radioisotope sources, sealed radioisotope sources ofmore than 1,000 times the Lower Activity Limits, radiation generators, andthe disposal of radioisotope wastes.
(2) Notification: The use of sealed radioisotope sources equal to or less than 1,000 times theLower Activity Limits and the sale of radioisotope source.
(3) Notification of Certification Equipment: The use of approved devices (ECD, calibration
source etc.) which is received the design certification before manufacture
and attached with certification label on the surface after manufacture.
Fig.2 shows the number of users categorised by organizations that were permitted by or has
notified the Authority since 1959 when the Law was enforced. The sudden increase in thenumber of users from 2007 is due to the introduction of the certification equipment notification
system in 2005. Table 3 shows the number of radiation generators in Japan where most of thecyclotron and the linear accelerator are used for medical purposes.
The use of radiopharmaceuticals is regulated by the Medical Service Law which isestablished by the Ministry of Health, Labor and Welfare. The number of users ofradiopharmaceuticals is shown in Table 4.

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FNCA Consolidated Report on Radiation Safety (Japan)(Number of users: Each category)(Number of users: Total)

Figure 2: Number of users by category of organizations permitted by and notified to NRA

Table 3: Number of radiation generators permitted by NRA(2012)
Generator

NumberCyclotrons

206

Synchrotrons

40

Synchrocyclotrons0Linear Accelerators

1,144

Betatrons3

Van de Graaff Accelerators

37

Cockcroft-Walton Accelerators

72

Transformer-type Accelerators

16

Microtrons9

Plasma Generators

1

Total

1,528

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FNCA Consolidated Report on Radiation Safety (Japan)

Table 4: Number of licensed hospitals and clinics for using radiopharmaceuticals

Year

2007

Hospitals &Clinics

2008

1,297

2009

1,293

2010

1,278

2011

1,281

1,273

1.3.2 Workers and Specialists in Radiation Facilities
1.3.2.1 Radiation Workers
Those who are given permission to use and dispose of radioisotopes, or who submit a
notification for the use, sale and rental of radioisotopes, or who are given permission to useradiation generator, must comply with a series of standards for safety control for effective
management of radiation hazards.
Specific requirements for workers entering controlled areas include: Education and training,measurements of personal dose and special medical examinations for radiation exposure. The
round number of radiation workers including x-ray device handlers is shown in Table 5. This
round number adds up the number of person that wore a personal dosimeter in published.
Table 5: Round number of radiation workers(Including x-ray device handlers, 2011)

Organization

NumberMedical (including veterinary medicine)

275,000

Research and Education

69,000Industry

63,000

Total

407,000

1.3.2.2 Radiation Protection Supervisors
In order to conduct appropriate and thorough radiation safety control, it is necessary to set up
a management structure responsible for radiation protection control within the establishment.
The radiation protection supervisor plays a key role in radiation protection control. Radiation
protection supervisors are the person responsible for undertaking the supervisory role in ensuring
the radiation hazards are effectively managed. They are appointed by all establishment whereradiation or radioisotopes are handled for use, sale, lease, or disposal.
To be qualified as a radiation protection supervisor, he or she must pass a national
examination and completes a training course. There are three classes of radiation protection
supervisors – first class, second class and third class. The class is required by a particular62

FNCA Consolidated Report on Radiation Safety (Japan)

establishment depends on the type of radioisotopes and level of radiation being handled. In
addition, radiation protection supervisors must attend seminars which are held regularly, in orderto keep abreast with 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 6 and 7 respectively. The number of successful
applicants in the national examinations for radiation protection supervisors (first class andsecond class) is given in Fig. 3 and 4.
Table 6: Contents of the national examinations for radiation protection supervisor (2012)
Class

Days

Subjects

Subject Items

First

2

6

Second1

3Law, Safety control techniques for radiation protection (1) and (2)

Third

-

-

No Examination

Law, Physics, Chemistry, Biology, Measurements and safety control
for radiation protection

Table 7: Regulatory training course for radiation protection supervisor (2012)
Class

Days

Enforcement Organization

First

5

JRIA, JAEA and ESC

Second3

NUSTEC and ESC

Third

2

JRIA, JAEA, NUSTEC and ESC

JRIA: Japan Radioisotope Association
JAEA: Japan Atomic Energy Agency
NUSTEC: Nuclear Safety Technology Center
ESC: Electron Science Institute63

Remarks

No Examination

FNCA Consolidated Report on Radiation Safety (Japan)(Number of examinees and successful applicant)(Ratio of successful applicants)

Figure 3: Number of successful applicant in national examinations for radiation
protection supervisors (First class)(Number of examinees and successful applicant)(Ratio of successful applicants)

Figure 4: Number of successful applicant in national examinations for radiation
protection supervisors (Second class)64

FNCA Consolidated Report on Radiation Safety (Japan)

1.3.3 Activity of Radioisotope Sources and Number of Radiation Generators
The total radioactivity of the main unsealed radioisotopes, sealed radioisotopes andradiopharmaceuticals distributed by Japan Radioisotope Association (JRIA) are shown in Figs. 5,
6 and 7, respectively. A general decline in the yearly total radioactivity distribution by JRIA
over the last several years can be observed.
(GBq: Each nuclide)(GBq: Total)

Figure 5: Amounts of major unsealed radioisotopes distributed by JRIA

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

Figure 6: Amounts of major sealed radioisotopes distributed by JRIA

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

Figure 7: Amounts of major radiopharmaceuticals (medical nuclides) distributed by JRIA

1.3.4 Recent Movement Concerning Radioisotope Sources
1.3.4.1 New Regulator
The regulatory role was transferred from the Ministry of Education, Culture, Sport, Scienceand Technology (MEXT) to the NRA on April, 2012. The NRA was established to absorb andlearn the lessons from the Fukushima Daiichi Nuclear Accident of March 11, 2011. The NRA is
the regulator responsible for the safe management of nuclear power plants and radiation
facilities.
1.3.4.2 Emission Material
By the Law, any material that is activated by a radiation generator to an energy level above
natural background, such as a target or a collimator, are regulated and must be collected by a
dedicated disposal service provider.
1.3.4.3 Discovery of Radiation Sources
Many beginners measure radiation using radiation detector since the Nuclear Power Plant
Accident. Because many people performed radiation measurement of the private or public place
where nobody had measure before the accident, some radiation sources which were not
managed were discovered. The radiation sources were Ra-226 which was used as luminous
paints before the laws are established.
1.4 Education and Training
1.4.1 The Law Concerning Prevention of Radiation Hazards Due to Radioisotopes, etc.
Radiation users provide radiation workers with education and training, (1) prior to their firstentry into controlled areas; and (2) at least once a year thereafter (re-education). Through there-education, radiation workers obtain the latest knowledge on regulations, radiation effects, and66

FNCA Consolidated Report on Radiation Safety (Japan)

techniques for safe handling, as well as have an opportunity to regularly reaffirm the importanceof safe handling.
Radiation users shall educate inexperienced radiation workers on the items listed in the
Table 8. The minimum education time for each item is clearly determined by the law.
Sometimes OJT (on-the-job-training) or special curriculum of practical training specific to eachfacility are provided for a more effective education.
Table 8: 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 facilityA
30 min
4 hrs
1 hr

B
30 min1.5 hrs
30 min30 min30 min

A: Radiation workers
B: Workers who do not enter controlled areas

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, specification, and operations of the related facilities and equipment
 Radiation management
 How to handle contaminated materials
 Emergency plan
 Nuclear security including physical protection, etc.
The minimum time for these education items 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 health and safety
education relevant to his scope of work. This is required by 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 health and safety education related to those
operations. These special operations include works carried out using X ray generators, or in
nuclear fuel facilities or nuclear reactors.
1.4.4 Examples of Education and Training
Below are examples of education or training offered in workplaces or universities toradiation workers.

1.4.4.1 Nuclear Power Plant
 Fundamental and practical knowledge (5 hours)

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FNCA Consolidated Report on Radiation Safety (Japan)

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 andprecise 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 for accuracy in order to ensure the safety and security of the people working
with ionizing radiation. Measuring instrumentations such as ionization chambers, scintillation
counters and semiconductor detectors are important in radioactive waste management and need
to be calibrated using reference radioisotope sources. Normally calibrations are performed bycalibration laboratories, where measuring devices are calibrated using reference instruments.
These reference instruments are in turn calibrated by reference 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 with highest accuracy, called national standards. Fromthe viewpoint of accuracy and reliability in measurement, it is essential to calibrate measuring
instruments and secure the traceability of measurement 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 9 shows the national standards on ionizing radiation andprimary instruments used in absolute measurement of each quantity. Accuracy and worldwide
consistency of the national standards were verified in multiple participations (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 of these1 http://www.nmij.jp/english/

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FNCA Consolidated Report on Radiation Safety (Japan)

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 forthe competence of testing and calibration laboratories) and peer-reviewed by experts from major
foreign national metrology institutes every four years. The calibration certificates issued onthese standards can be accepted worldwide within the range specified in the Calibration andMeasurement 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 calibrationlaboratories (i.e. secondary standards) with national primary standards. In the calibrationlaboratory accreditation system, calibration laboratories are assessed and accredited asaccredited calibration laboratories to meet the requirements of the measurement act, relevant
regulations and ISO/IEC 17025. Calibration laboratories are also required to periodically takeassessment as well as proficiency testing. Calibration certificates with a JCSS symbol issued byaccredited calibration laboratories assure the traceability to National Measurement Standards aswell as a laboratory's technical and operational competence and are acceptable worldwide
through the MRA of the International Laboratory Accreditation Cooperation (ILAC) and theAsia Pacific Laboratory Accreditation Cooperation (APLAC).

2 http://kcdb.bipm.org/AppendixB/
3 http://kcdb.bipm.org/AppendixC/

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FNCA Consolidated Report on Radiation Safety (Japan)
Table 9: 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 the relevant government ministries before operating thefacility.
The facilities are required to record and check the measurements during practical operation
using a radiation monitor such as gas monitor. Therefore, almost all RI facilities in Japan
employ radiation control systems to simplify the management and automation of record
keeping.
The radiation safety control system is employed in combination with the following systems
in accordance with intended use.
a. Radiation Monitoring System (Fig.8)
The radiation monitoring system consists of an area monitor that monitors equivalent dosein a controlled area and a room gas monitor that monitors radioactive concentration in theoperating room. In addition, a gas monitor that monitors radioactive concentration of gas
discharged from facilities to the public, and a liquid monitor that monitors radioactive
concentration of effluent are part of the system.

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FNCA Consolidated Report on Radiation Safety (Japan)

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.9).

Operation console

Figure 8: Configuration of Radiation Monitoring System

Figure 9: 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 that access
RI facilities and controls access records by identification (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 area of
RI facilities. The system can be set up to define the authorized access area and period for eachqualified radiation worker.
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 no contamination is detected.
The system is used in combination with limit switches on doors or key switches aspersonnel access the facilities where interlocks are required. It is used as a part of an interlock
system to prevent accidental startup of equipment when radiation workers are in specificrestricted areas relative to the equipment.
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 of workers can be calculated by checking the data of personnel working incontrolled areas including their access times in the controlled area on specified dates andtimes. In addition, contamination or a loss of radiation sources can be determined with data
traceability.

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d. Unsealed Radioisotope Stock Control System
The unsealed radioisotope stock control system is mainly used in RI facilities because thesystem unifies the management of procurement, acceptance, storage, utilization, disposal anddelivery 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 oryear) for storage and specifies by whom, when, and where each source is used and thequantity 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.10).
Recently, a stock check system using the RI stock list, noncontact IC tag and handy
terminal was introduced (Fig.11). 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).

Figure 11: Stock Control System

Figure 10: System Control Display

e. Personal Dose Control System
The purpose of the personal dose control system is to streamline the evaluation of effective
dose at the facility. Measurements of personal dosimeters and the results of periodic healthcheck-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 who have exceeded thedose limit can be detected so as to prevent them from entering the access control area.
In addition, a personal dose control system utilizing an electronic dosimeter, which is also
used in the dose evaluation at nuclear power plant etc., has started to become widely used.
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 dosimeter (It is measured and evaluated every monthwith glass badges and other methods. This work is generally outsourced.) and by the periodic
health check-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
identifies/quantifies exposure after the occurrence. It is important to emphasize radiation
protective measures based on exposure minimization in work area more assertively.
Therefore, employment of aforementioned personal dose control system using the electronic
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radiation exposure promptly.
2.1.3 Radiation Protection at Work Area
Environmental monitoring at the work area is conducted for radiation protection and themethods employed are described below. The monitoring is required in order to not exceed themonthly-base limit set within the laws and regulations. The monitoring can be conducted by
Manager, but it is mostly outsourced.
2.1.3.1 Measurement of Airborne Radioactive Concentration
Airborne Radioactive Concentration is measured by filtration method with movable dust
sampler. It is used to measure internal exposure and is implemented in a room where there is apossibility the worker would inhale the RI, such as rooms using RI. For area with high airborne
contamination level, room gas monitor or iodine monitor is installed for real-time monitoring.
2.1.3.2 Surface Contamination Measurement
Surface Contamination is measured directly by smearing or the survey meter. It is required
to measure the surface contamination of the monitoring room (which is the entrance to therestricted 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 eg. entrance ofeach operating room. Hand foot monitor detects floor surface contamination by measuringpersonnel wearing work area slippers, so that contamination status is immediately recognized.
If any contamination was detected, the area is immediately secured to prevent further
spreading of the contamination and to enable the decontamination of the area to be carried out..
Results of contamination surveys of the work areas are provided to all workers to provide
awareness.
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 the boundaries
of controlled areas and site.
Area monitors are installed in areas of potential high dose equivalent rate, areas with large
dose rates fluctuations, in locations where personnel stay most of time and at boundaries ofcontrolled area. In many cases, the area monitor provides real-time data to the radiation
monitoring display 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 RI facilities 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. The law also requires radioisotopes (RI) facilities to establish an exclusion
boundary area (reasonable distance from public domain) including the residential area for RI

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facilities workers, with an effective dose level not to exceeding 250 uSv per 3 months.
2.1.4.2 Medical Sector
Guidelines (residual radioactivity and dose rate) and safety instructions related to therelease of patients administered with unsealed radionuclides and 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 may
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 of entry andexit 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 for orphan
sources and radioactively contaminated scrap metals.

Figure 12: Image of truck radiation

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 thenormal operations of a facility, for example the loss of regulatory control of a radiation source.
This accident may be caused by earthquake, fire and other hazards/disasters (flood and power
failure etc), deliberate offense like theft and pilferage, and machine failure.
Measures in the event 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), as well as other government agencies. Should these
events occur, the employer is required to report promptly to a jurisdiction ministry andrelated organizations.
2.1.5.2 Examples of Accidents while Using RI at a Nuclear Medicine Facility andTransporting (emergency situation)
Below are examples of possible emergency situations whilst using RI:a) The possibility of a fire causing vaporization and evaporation of radioactive materials.
b) Inability to terminate irradiation promptly due to damage of shielding materials caused by74

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an earthquake during the irradiation process.
c) A radiation source has fallen out of its container.
d) Inability to return the radiation sources back to their containers due to malfunction of
remote controllers.
e) A radiation source is missing due to theft or loss.
f) Faults or damage to local exhaust ventilation system or the emission source enclosuresystem.
g) Loss of radioactive substance due to leakage or spillage.
2.1.5.3 Reporting
The line of reporting varies according to jurisdiction or cases. Relevant authorities may
include the Ministry of Education, Culture, Sports, Science and Technology (MEXT), labor
standards offices in the respective jurisdiction, police stations, fire departments, Ministry ofLand, Infrastructure, Transport and Tourism, public health department, and the National
Personnel Authority.
2.1.5.4 Medical Examination etc. (Ordinance on Prevention of Ionizing Radiation
Hazards)
The employer shall ensure workers falling under any one of the following categories
receive immediate medical attention and submit a report to the relevant head of the labor
standards office.
 Those who were in the area when the accident occurs.
 Those who have been exposed above the effective dose or equivalent dose limit.
 Those who have accidentally inhaled or ingest radioactive materials.
 Those whose external contamination level fails to fall below one tenth by means ofwashing and so on.
 Those who has contaminated wounds.
2.1.5.5 Discovery of radioactive materials (response to accidents regarding orphan
sources)According to the radiation hazards prevention law, a permission or notification is required
for the use radiation materials above a specified quantity. MEXT requests, both on theirwebsite and through other media, for the public to report on any suspected radioisotopes
materials they find and warns against touching or moving them without authorized direction.
The following information are to be collected by MEXT if a radioactive material isreported: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 measured, radiation survey meter or measuring instrument used, andmeasurement method employedg) Description of the area surrounding the suspected source (if there is a house or not etc.)75

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2.1.5.6 Preparation of radiation emergency response manuals
In RI applications facilities, radiation emergency response manuals and checklists areprepared and disseminated among the workers in case of an accident. The following cases are
considered in the document.
a) Fireb) Earthquakec) Need for Ambulance vehicled) Radiation exposure (loss of radiation sources, irradiation shutdown failure due toequipment malfunction, inadvertent external and internal exposure, personal
contamination)e) Dispersion of contamination of unsealed sources（gas, dust, and liquid）
f) Loss or theft of sourcesg) Discovery of orphaned RIh) 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 the Regulationof Nuclear Source Material, Nuclear Fuel Material and Reactors of Japan as well as Nuclear
Power Plants. The radiation safety procedures are ruled in the inside-rule of every facility, butmuch simple relative to those of NPPs.
The radiation safety management at the reactor facility consists of the management ofradiation workers, radiation control of work 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 a controlled area equipped with radiation protection
equipment, 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
at a lower level relative to the outside so that radioactive materials cannot flow out to thegeneral area. For most research reactors, the criticality monitoring is not necessary except at
special critical assembly facilities. Access control for workers is restricted and all workers
entering the reactor room are logged for the duration of their stay in the room. On exiting thereactor room, both staff and items removed from the room are monitored and cleared forradioactive contamination. Exposures of workers above a set exposure value are reported.
All radiation workers have to wear an experimental or working suit and safety shoes toavoid contamination of their own bodies and clothes. The radiation workers must also wear
either one or two types of personal dosimeters to measure and record their exposure values.
Direct reading personal dosimeters are useful for individual exposure control. The radiation andair contamination (dust or gas) monitoring equipment are often used to monitor the status of theworking area. If the air contamination level exceed a designated criterion, appropriate radiation
protection measures, such as wearing air mask etc. are taken. When work is finished,
contamination surveys are carried out on work surfaces, tools, floors and personnel using survey
meters.

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2.2.3 Radiological Protection for Radiation Area
Radiation protection officers regularly monitor the radiation and air contamination levels at
the work area. These data are collected by radiation monitors and electronically recorded. In an
event of an abnormal excursion from the set limits, the radiation protection officers would notify
the workers of the situation and direct them to take the necessary protective measures. Figure
13 shows an example of air contamination monitoring at a controlled area.

Figure 13: An Example of Air Contamination Monitoring at a Controlled Area

The control of radioactive materials discharge to the general environment is also important
for research reactors. The discharge limit for each facility is governed by its respective license
held. However the actual radioactivity discharge is often much lower the set limit. For someresearch reactors, the main radionuclides in their atmospheric and effluent discharges are Ar-41
and tritium (H-3). Fission products, such as I-, Xe-, etc., are discharged into the atmospherefrom general water-cooled type research reactors. Figure 14 shows an example of the air
monitoring system for a research reactor facility. The radioactivity level in the air is constantly
monitored using dust or gas monitors. Dust and volatile materials are also sampled with air
filters. The filters are measured using devices such as Ge detectors and/or gas flow counters toprovide a comprehensive radioactivity concentration level.
The liquid waste from the controlled area is first stored in a holding tank at each facility andsampled to determine the activity level. If the level of radioactivity in the liquid waste is lessthan a designated level, the liquid waste is discharged into the sea. If the designated value is
exceeded, the waste is transferred to the disposal treatment facility.

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Figure 14: An example of monitoring system for airborne radioactive waste at research reactor facility

2.2.4 Radiological Protection for the Public
Exposure to the public is evaluated based on atmospheric and liquid discharges. The amountof radioactivity discharge and the evaluated dose to the public are reported to the Government
and the local governments. In addition, most of the organizations that operate research reactors
set up environmental stations or posts both internally and external to the site, for ongoingobservation of parameters such as radiation level and others.
2.2.5 Radiation Emergency Preparedness
In emergency situations, such as fire, earthquake or any disturbances within the facility, allof that facility must gather immediately and engage in the recovery work. The training on
emergency preparedness is also conducted once or twice every year to maintain workers’
motivation.
2. 3 Radiation Management in Nuclear Power Plants
2.3.1 Radiation Safety Management System
The radiation safety management system of nuclear power plants is headed by the director.
Fig.15 shows an example of the system.

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Figure 15: Radiation Safety Management System

2.3.2 Radiological Protection for Radiation Worker
In the nuclear power plants, the doses for radiation workers are managed within the legal
dose limits of 100 mSv over 5 consecutive years and 50 mSv in a single year, as well as theplanned 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 to provide their past dose history,
medical reports, education records demonstrating knowledge of radiation and rules for working
with radiation and so on. Only after verification of the above, they can be permitted to work inradiation-controlled areas.
After the registration, they undergo periodic medical examinations, external dose checks byelectronic type pocket dosimeter or glass badge and internal dose checks by whole bodycounters. Then the total amounts of personal exposure doses are reported to each individual
worker.
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.16). For each person, Radiation Dose Record
Booklet (Radiation Passport) is issued by agencies authorized by the RADREC. The booklet
contains necessary information for radiation protection management such as the worker’s
identification, historical exposure results, educational records and so on.

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Radiation Dose Registration
Center for Workers

Registration/Referral

ReportBooklet issuing
institution

ReportStation A

Station B
NoticeWork

Work

NoticeBooklet issue
Bringing

Bringing

Figure 16: 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

Figure 17: Radiation Management Work Flow (From plan to report)

Fig.17 shows the radiation management work flow. By each step,Plan-Do-Check-Action (PDCA) is repeated conventionally to reduce exposure dose.

the2.3.3 Radiation Area Management
Unnecessary exposures are prevented by setting radiation-controlled areas where the total
effective dose from external radiation or radioactive materials in air and surface density ofradioactive materials can exceed or be suspected to exceed the legal limits. The dose rates in theradiation-controlled areas are determined by setting up radiation monitors for continuous
measurements and monitoring. To determine the level of the contamination, surface
contamination level of the structural objects or in the air are measured and monitored.
According to the dose rates and contamination levels, the radiation-controlled areas are divided
into different categories using walls and fences with signage.(Fig.18)
To prevent accidental taking out of radioactive materials from radiation controlled areas,
radiation worker are required to remove the personal protective clothings and shoes etc. upon

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exiting, and check themself for contamination when they exit from the radiation controlled areas.
Items removed from a controlled areas have to be checked also.

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 Dosimeter

Figure 18: 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
Table 1 shows the annual dose limit (1mSv/y) for the public. The limit is set by theregulation to ensure the protection of the public against radiation from nuclear power stationsin Japan. This is based on ICRP recommendation in 1990.
To allow for compliance with the regulation by a wide margin, a dose target of only
50μSv/y has been set for the public in a separate guideline, described in the Nuclear Energy
Special Committee report. This is the target public dose value for the radioactive 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).
(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 reactor site suitability
and design adequacy.
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 10. The severe accident is defined as an accident that is less likely to occur. The

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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 10: The dose limits for the public in the Japanese regulation and guidelines.
Type
Regulation (limit)
Guideline(targetvalues)

Dose criterion

Annual dose

1 mSv/yDuringnormaloperationAnnual dose for release of radioactive
materials

50 μSv/yAnnual dose for radiation from facilities

50 μGy/y

Under
accident
condition

Designaccidentbasis

Severe accident
Hypotheticalaccident

Effective dose

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 equipment, and radiation monitoring andsampling systems are provided at nuclear power stations to establish radiation safety for
public and radiation workers. The releases reduction systems and the radiation protection
equipment 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 the guidelines.
In case of an abnormal event, the systems and the equipment 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 the technicalsupport center to allow operational actions. Furthermore, the releases reduction systems andthe radiation shielding facilities are provided to ensure compliance with the dose targets set in
the guidelines for abnormal condition.
(b) Radiation protection design(i) Releases reduction systems
Releases reduction systems are designed so as to contain radioactive gaseous waste
emitted as a result of the degassing process of the reactor coolant, to monitor theconcentration 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.

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Reactor coolant, equipment drains, floor drains and effluents from hand-washing,laundry, and hot shower systems are filtered, demineralized and concentrated by theevaporator. This is to ensure that the concentration of radioactive materials in the liquid
waste is sufficiently reduced. The liquid waste is then diluted and released after a final
check on the radioactivity level. The concentrated liquid waste generated from theevaporator is solidified. The miscellaneous solid waste and the spent exhaust filters arecompacted for volume reduction. The low level spent resin, low level concentrated liquid
waste, and combustible miscellaneous solid waste are incinerated for volume reduction.
These solid wastes are put in packed drums for temporary storage. Sufficient storage
capacity has been reserved for the storage of high level spent resin generated throughout thelife of the plant.
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 of releases
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 ensuring effective shielding of the radiation equipment or facilities. In reactor facilities,
the shielding 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
discharging of wastes. 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 the 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 detection are
installed in the reactor coolant, main steam, waste treatment, and ventilation systems.

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Grass (sample)
Soil (sample)
Water (sample)

Site boundaryLand
Monitoring post
Sea

Nuclear power station

Fish (sample)

Figure 19: 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, notification
obligations during the abnormal event, declaration of a nuclear emergency, mechanisms forsetting 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 the lossof 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 area 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 the organization of Nuclear Emergency Response Headquarters within thegovernment, Local Nuclear Emergency Response Headquarters at the Off-site Center, and a
Joint Council 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

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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, to establish
a thorough preparedness structure in case of nuclear disaster, nuclear emergency response drills
are regularly conducted jointly by the central government, local governments, operators, andother parties concerned to make sure that the communication system, command system,
decision-making process, evacuation process, and roles and functions of individual participants
work effectively.
National Government

Prefectural

Nuclear Emergency Response Headquarters

Emergency Response Operations 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

Figure 20: Emergency Preparedness Organization

2.3.5.3 Response to a radiation accident
Possible radiation accidents at nuclear power stations include excessive exposure andradioactive contamination during normal operations inspections, periodic inspections ofradioactive equipment, and handling of spent resin, spent filters and other radioactive waste.
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 of85

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high safety awareness and reduced exposure time.
In case a radiation accident occurs, the top priority is placed upon the safety of humans andlifesaving. 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 theaccident 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 located at Rokkasho-Mura, Aomori Prefecture, is different
from the one applied to nuclear power plants in that its applied method changes in accordancewith 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 twodifferent types of waste packages are buried. In No.1 Facility, liquid waste such as waterused in rinsing the floor of nuclear power plants is evaporated, concentrated and solidified,then 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 eachwaste package, but the level is below the upper concentration limit defined by law. The
actual activity is confirmed before transportation from nuclear power plants, with proper
signage indicating its content (ie. radioactive waste) and identification number on the
package. Upon arrival at Rokkasho Disposal Facility, Government confirmation that eachpackage conforms to technical 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 for load bearing ability.
4) That signs and identification numbers are in place.
 Regarding the disposal facility
Waste packages are placed inside the disposal facility (pit) made of reinforced concrete.
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.
, After confirmation of waste packages upon reception, the individual packages do notneed to be verified after their disposal, since radioactive waste in principle attenuates

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according to its half-life, and since the evaluation and control of dose to the general public is
conducted on the disposal ground as a whole.
After waste packages are fixed fully inside a pit, spaces between the drums are filled inwith mortar, and further cover made of reinforced concrete is placed over the entire disposal
facility, providing shielding for the radioactive waste completely. The entire facilities iscovered with water-impervious Bentonite clay．This is then backfilled with the original soil
and overlay with grass, and will remain a controlled site for approximately 300 years.
 Regarding Phased Management
In "Phased Management" the waste disposal facility is managed differently according to
the following three phases:
In the First Phase, where the radiation level at the start of burial is not sufficiently low,
waste packages are shielded by means of artificial barriers such as concrete pits and drums,
so as to prevent radiation and radioactive material leakage.
In the Second Phase, upon completion of the First Phase, radioactivity becomes low after
the passage of certain period of time, 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.
In 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 becomes very
low, safe enough to negate the regulatory control of the waste packages as radioactive
material.
Figure 21: Attenuation by aging of total radioactivity

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Table 11: 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
Measures relative to both the facility and management are undertaken as follows:
Related to facility:
・Shielding, in accordance with the area of access by workers.
Design criteria for shielding are as follows:
Table 12: 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.
・Crane for the handling of waste packages and inspection equipment of waste packages are88

FNCA Consolidated Report on Radiation Safety (Japan)

automated and remote controlled.
・Entry-exit Control Units and Radiation Measurement Equipment are installed for the
management of occupational exposure.
Table 13: 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.

Related to management: 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 monitoring 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 due to the leakage of radioactive material
from the Disposal Facility, it is important that there should not be harmful impact on humanenvironment through groundwater.
The Rokkasho Disposal Facility is located in an impermeable bedrock called the"Takahoko Layer" which is distributed several meters below the land surface, hence thegroundwater flows mainly near the surface only. Since the landscape is a plateau surroundedby rivers and marshes, the groundwater consists mainly of rainwater which has seepedslowly underground. Groundwater is not abundant in this area.
Given that waste packages are placed in pits made of concrete, where the spaces inside
the pit are filled by mortar, and pits are surrounded by soil mixed with bentonite, sufficientmeasures are taken to prevent seepage of groundwater. Also, even in the unlikely event ofgroundwater seepage into the Disposal Site, the water seeping through the surrounding
porous concrete can be drained before it can reach the waste packages until the Second
Phase. It is therefore unthinkable that the radioactive material can leak easily out of the
Disposal Facility.

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FNCA Consolidated Report on Radiation Safety (Japan)

Table 14: 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.

Table15： 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 scenario where radioactive material leaks prematurely,
evaluation of the impact on consuming maritime products from the marsh (which is the end
point of the ground water migration) has been 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 theprovisional target.

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FNCA Consolidated Report on Radiation Safety (Japan)

Dose equivalent evaluation is undertaken based on the 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 thateven taking into account the multiple intake routes, the dose equivalent is 0.13 micro Sv/year,
a value too to effect an impact.
Table 16: 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 17：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
Dairy Products
using marsh water
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

91

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)

Figure 22: 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 waste varies in materials and radioactivities.

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. prior
to discharge under the radiation monitoring into the atmosphere.
Liquid waste with radioactivity concentration below the discharge limits is released into theenvironment. Other liquid waste is treated at the liquid waste treatment facilities.The
concentrate and sludge are solidified into a container (drum), and the treated liquid isdischarged into the environment.
Treated liquid
Concentrate
SludgeEvaporation

Sedimentation

Filtration

92

Solidification

Radioactivity
measurement
Discharge

FNCA Consolidated Report on Radiation Safety (Japan)

All of solid waste is transported
Large size
Combustible
Incombustible
to the waste treatment facilities.
Incombustible waste is compressed,
combustible waste is incinerated,
and large size waste is cut andsorted before being packed into
containers. High radiation dose
waste is handled in shielded cells
Dismantling
Incineration
Compression
and packageed into a shieldedcontainers.
The packaged waste is stored in the storage building. They are checked periodically on aregular basis and maintained in a safe condition.

Storage & Radiation Control

2.4.3 Radioisotope Waste Management Generated from the Use of Radioisotope andRadiation
In Japan, Japan Radioisotope Association (JRIA) supplies sealed radioisotopes and unsealed
radioisotopes including radiopharmaceuticals to users all over the county. Radioisotope waste
and disused sealed radioisotope sources are generated after the use of unsealed radioisotopes
and sealed radioisotopes. JRIA is also in charge of collection and treatment of the radioisotope
wastes, and return of disused sealed radioisotope sources. JRIA maintains the complete systemfrom supply of radioisotope products to treatment of their wastes. JRIA takes a special part in
the distribution of radioisotopes in Japan. The Japanese system of radioisotope use and JRIA’srole is shown in Fig.23.

Figure 23: The Japanese system of radioisotope use and the JRIA’s role93

FNCA Consolidated Report on Radiation Safety (Japan)

Users sort out the radioisotope wastes according to the prescribed categories such as
combustibles, compressible, animal carcasses and so on and put them into the special containers
provided by JRIA beforehand. Users supplies registration card describing the contents within
the waste containers. The packaged radioisotope waste containers with the registration cards arecollected by JRIA. The categories of radioisotope wastes are shown in Table 18. They areshipped from the users’ establishments to the JRIA’s storage facilities by truck and stored until
their treatment. Only a proportion of the radioisotope waste collected from research andindustrial establishment (non-medical radioisotope waste) is treated by JRIA. However all theradioisotope waste from medical establishment (medical radioisotope waste) is treated at Kaya
Memorial Takizawa Laboratory of JRIA. A large proportion of the non-medical radioisotope
wastes is stored for further treatment at the several storage facilities belonging to JRIA. The
final disposal route of the treated wastes is currently under being evaluated and the government
will make its decisions in the near future.
JRIA collected about 9,000 drums (200 liter drum) of radioisotope wastes in 2012. About
3,900 drums of those were shipped from medical establishments. Forty percent of which were
combustible.
Table 18: Categories of Radioisotope Wastes
Category
Solid

LiquidMaterials

Container

Combustibles Ⅰ

Paper, Cloth, Wooden, chips,
etc.

50 L Steel drum

Combustibles Ⅱ

Plastic tube, Plastic vial,
Polyethylene sheet, Rubber
glove, etc.

50 L Steel drum

Incombustibles (Compressible)

Glass vial, Glass ware,
Syringe, Needle, PVC tube,
etc.

50 L Steel drum

Incombustibles (Non-compressible)

Soil, Sand, Pebble, Concrete
garbage, Scrap metal, etc.

50 L Steel drum

Animal carcasses

Dried animal carcasses

50 L Steel drum

Filter (Combustibles)

HEPA filter,
Charcoal filter

Filter (Incombustibles)

HEPA filter, Pre filter

50 L/ unity

Charcoal filter (Incombustibles)

Charcoal filter

50 L/ unity

Inorganic liquid

Liquid waste generate byexperimental use

25 L PE bottle

Organic liquid

Liquid scintillator waste

25 L Stainless drum

94

Pre

filter,50 L/ unity

FNCA Consolidated Report on Radiation Safety (Kazakhstan)

6. Kazakhstan
Part 1. Radiation Safety in RI Facilities .............................................................................................. 96
1.1. General ................................................................................................................................. 96
1.1.1 Legislative Framework and Policy for Radiation Safety .................................................. 97
1.2 Outline of Radiation Facilities and Radiation sources ......................................................... 98
1.2.1 Number of specialists and workers in related organizations ............................................. 98
1.2.2 Number of radiation facilities including related facilities ................................................. 98
1.2.3 Activity and number of radiation sources and generators ...............................................100
1.3 Education and Training .......................................................................................................100
1.4 Standardization on radiation and radioactivity ...................................................................100
Part 2. Status of Radiation Safety Management ...............................................................................101
2.1 Radiation safety management in various RI usage.............................................................101
2.1.1 Radiation Safety Management System............................................................................101
2.1.2 Radiological Protection for Radiation Worker ................................................................101
2.1.3 Radiological Protection for Radiation Area.....................................................................102
2.1.4 Radiological Protection for the Public .............................................................................102
2.1.5 Radiation Emergency Preparedness ................................................................................102

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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 statute 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 safety of nuclear activities;- 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 the verification.
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.
Republic of Kazakhstan is a member of Nuclear Suppliers Group (NSG). The legislation,
standards and rules for nuclear export control therefore correspond to all NSG recommendations.
All nuclear export and import applications shall be agreed by the Committee – the license isissued by the Ministry of Industry and Trade. It shall be noted that sale of nuclear or otherradioactive materials and radiation 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 thefield of atomic energy use. Isotope products are used in various fields of economy mainly asso-called ampoule sources of radiation.
Some of the most important conditions for the safe use of atomic energy are legal regulation,
responsibilities allocation between organizations engaged in atomic energy use and state bodies
monitoring the nuclear and radiation safety.
The Committee is entitled to grant license for activities related to atomic energy use and tosupervise over the licensing requirements execution within its jurisdiction.
The primary activities in the field of atomic energy are 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. 716 dated July 10, 2013.
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 andaimed to protect humans` health and life, environment and to provide nuclear weapons
nonproliferation and nuclear 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 activities and establishes the necessary licensing of all types of atomic energy
activities.
The Law "About Radiation Safety" (No. 219 dated to April 23, 1998) regulates public

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FNCA Consolidated Report on Radiation Safety (Kazakhstan)relations in the field of radiation safety to protect the health of population from negative impact
of radiation and sets the main 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 theradiation 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 and sets the list of documents necessary to get thelicense.
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 the main principles of radiation safety. The Law establishes the jurisdiction of
the state bodies on provision of radiation safety, general requirements for radiation safetyassessment and radiation safety when using the radiation sources.
The Resolution of the Government of the Republic of Kazakhstan (No. 716 dated July 10,2013) "Qualification Requirements to Activities Subject to Licensing in the field of the use of
Atomic Energy” establishes the list of activities subject to licensing by the Committee ofAtomic Energy (in compliance with the Law “About Atomic Energy Use”), qualification
requirements to applicants for activities related to atomic energy use and the list of documents
necessary to get the license.
The number of staff works for Committee is 60 persons including the Chairman and two
Deputies. There are 11 divisions under the Committee–Licensing, Review and Inspection,
Material Control and International Guarantees, Nuclear Physical Security, TechnicalCooperation, Informative Provision, Atomic Industry, Atomic Energy, Scientific and TechnicalDevelopment, Administrative and Legal, and Financial.
1.2 Outline of Radiation Facilities and Radiation sources
1.2.1 Number of specialists and workers in related organizations
The total number of people working with radiation related industry in Kazakhstan is difficult
to define correctly now. However a number of workers and a number of radiation
workers under the personal radiation monitoring service are available for basic
Kazakhstan`s organizations in the field of atomic energy such as National Atomic
Company “Kazatomprom” (the national operator of the Republic of Kazakhstan forimport and export of uranium, rare metals, nuclear fuel for power plants, special
equipment and dual-purpose materials), National Nuclear Center of the Republicof Kazakhstan and Institute of Nuclear Physics. Currently the total number ofworkers in these organizations is approximately 28,000 and 6,500 of which is under
the personal radiation monitoring service.
1.2.2 Number of radiation facilities including related facilities

National Nuclear Center (NNC) was created by presidential decree in May 1992. The NNC
is responsible for conducting research on the peaceful use of nuclear energy and radiation safety
and is also responsible for evaluating the consequences of nuclear tests at the now-closed
Semipalatinsk Test Site.

98

FNCA Consolidated Report on Radiation Safety (Kazakhstan)In accordance with the Government Decree three independent enterprises were created in
November 2012 under the NNC. They are Republican State Enterprise, National Nuclear
Center, Republican State Enterprise “Institute of Nuclear Physics” and Republican StateEnterprise “Institute of Geophysical Research.”
Institute of Nuclear Physics operates the VVR-K research reactor in Alatau.
NNC oversees the following institutes:- Institute of Atomic Energy: Includes the following nuclear research reactors: IVG-1M,
non-operational RA, and IGR;
- Institute of Radiation Safety and Ecology.
The pool type reactor on the thermal neutrons VVR-K uses demineralized water as aheat-carrier, moderator and reflector. It was put into operation in 1967 and worked on thermal
capacity of 10 MWt till 1988 without any deviation from the normal modes. From 1988 to 1998
works on strengthening the safety in conditions of high seismicity (calculations andsubstantiations, strengthening of designs, duplication of the systems responsible for the safety,
registration of the new documentation) had been done. By the configuration change of theactive zone, the thermal capacity has been reduced to 6 MWt without loss of neutron flows.
Water-cooled reactor IVG.1M which 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 the upgrading period 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 ionizing radiation ampoule sources (IRAS) repository in Kazakhstan was installed in
1995. The repository allowed the long-term safe storage (about 50 years), handling and disposalof spent IRAS, widely applied in industry, science, medicine etc.
The repository is located at research reactor complex “Baikal-1” on the territory of former
Semipalatinsk Test Site. Complex “Baikal-1” is situated at 75 km from nearest inhabited locality.
It is bounded by protective perimeter, provided with up-dated physical protection and guarded
by forces of Ministry of Internal Affairs Republic of Kazakhtan.
Spent IRAS , 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 cell and 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 at
the territory of complex “Baikal-1”.
The repository allows the improvement of ecological environment in many regions of
Kazakhstan and revives the cancer detection centers. By now over 40000 spent IRAS, including
30 oncological ones and over 2000 Cu each are accepted.
After shutdown of BN-350 reactor facility (MAEC site, Aktau), the issue of packing anddisposal of spent nuclear fuel (SNF) assemblies is arisen for the Government of Kazakhstan.
Research reactor (CRR) Complex “Baikal-1" situated at 75 km from Kurchatov was chosen
by the Republic of Kazakhstan Government to locate long-term spent nuclear fuel storage99

FNCA Consolidated Report on Radiation Safety (Kazakhstan)(LTSNFS) facility. The spent fuels were placed in packaging storage sets (PSS). Eight-seatferroconcrete dual-use casks (DUC) were used as suggested by the USA as a PSS. Spent fuels
were placed into the 60 containersand were shipped by rail transport.
RD Construction of SNF handling site including transfer site and storage site had beendeveloped by RD department. 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.
Transportation and placement for long term storage of 60 PSS with SNF were completed in
November 2010. Physical protection of nuclear material, radiation safety and optimal technicalstorage conditions are provided.
1.2.3 Activity and number of radiation sources and generators

The number and activity of sources in use now have not yet been clarified. These
information will be presented after analyzing and summarizing them.
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
is developed to increase the volume and nomenclature of RAW accepted for processing andstorage.
1.3 Education and Training
Radiation workers and personnel having access to radiation facilities shall attend appropriate
radiation protection training courses in both theoretical and practical aspects to acquire
radiation-handling skills neededfor access to controlled areas. There are 20 organizations indifferent regions of Republic of Kazakhstan which provide radiation protection officers training
courses. The duration of courses is usually 1-2 weeks. The Kazakhstan Atomic Energy
Committee has issued the document named “Common Requirements for Organizations
Providing Training for Personnel Involved in the Field of Atomic Energy in the Republic of
Kazakhstan”. The purpose of this document is to state the regulatory requirements for training
centers to establish and maintain training and qualification programmes for personnel involved in
activities in relation with the use of atomic energy in Kazakhstan. These requirements are applied
to training centers who provide training for nuclear facility personnel, permanent or temporary
employees, including contractors, experts and consultants at a site of any nuclear facility.
1.4 Standardization on radiation and radioactivity
Metrology laboratory of Institute of Atomic Energy of National Nuclear Center of100

FNCA Consolidated Report on Radiation Safety (Kazakhstan)

Kazakhstan was officially recognized by authorized state governmental agency as qualified andauthorized 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,
physical and 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 the
specific standards, codes and guides.
Basic list of normative technical documents of Atomic Energy Committee related to fueland radiation safety use in Republic Kazakhtan:
 Hygienic regulations “Sanitary–Epidemiological requirements to Radiation Safety
Assurance”, Government Decree, February 3, 2012, №201
 Sanitary rules “Sanitary–Epidemiological requirements for Radiation Safety Assurance”,
Government Decree, February 3, 2012, №202
 Sanitary rules “Sanitary–Epidemiological requirements for Radiation Dangerous Facilities”,
Government Decree, March 11, 2012, №308
 Technical requirement “Nuclear and radiation safety of research nuclear facilities”,
Government Decree, July 1, 2010
 Technical requirement “Nuclear and radiation safety of NPP”, Government Decree, July 1,
2010
 Technical requirement “Nuclear and radiation safety”, Government Decree, July 30, 2010
2.1.2 Radiological Protection for Radiation Worker
Radiation protection of workers need to be monitored to ensure that the total amount of
external and internal exposure does not exceed yearly limit of effective dose by using personal adosimeter and regular medical check need to be done in accordance with the applied
regulations.

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Table 1: Radiation dose limits for radiation worker and public

Application
Effective dose

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

Dose limit
Occupational
20 mSv per year, averaged
over a period of 5 consecutive
calendar years but not morethan 50 mSv per year

Public1 mSv in a year, averaged overa period of 5 consecutive
calendar years but not morethan 5 mSv per year

150 mSv
500 mSv
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.
2.1.4 Radiological Protection for the Public
The licensee shall ensure that exposure to public is in accordance with the Kazakhstan
norms and rules. Annual dose limit (1mSv/y) for the public given in Table 1 in accordancewith Kazakhstan regulation 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 radiation monitoring,which pulled a problem in the following: Assessment of effects of ionizing radiation on personnel and individuals from the
population;
 Determination of pollution levels in the environmental, equipment, clothing, industrial
and residential 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
a radiation accident); On the amount of radiation control, depending on group accident.

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7. Malaysia
Part 1. Use of Radiation Sources and Radiation ...............................................................................104
1.1 General ................................................................................................................................104
1.1.1 Legislative framework and policy for radiation safety....................................................104
1.1.2 Structure and System (Regulatory organizations) ...........................................................104
1.2 Outline of Radiation Facilities and Radiation sources .......................................................105
1.2.1 Number of specialists and Workers in related organizations ..........................................105
1.3 Education and Training .......................................................................................................105
1.3.1 Radiation Industry usage..................................................................................................105
1.3.2 Radiological protection ....................................................................................................106
1.4 Standardization on radiation and radioactivity ...................................................................106
1.4.1 External radiation andpersonnel dosimetry .....................................................................106
1.4.2 Calibration Facilities ........................................................................................................106
1.4.3 Calibration of Radiation Instruments...............................................................................109
1.4.4 Accreditation of Laboratory ............................................................................................. 111
Part 2. Status of Radiation Safety Management ............................................................................... 111
2.1 Radiation Safety Measurement in Various Radioisotope Usages ...................................... 111
2.1.1 Radiation Safety Management System............................................................................ 111
2.1.2 Radiological Protection for Radiation Workers............................................................... 112
2.1.3 Radiological Protection for Radiation Area..................................................................... 112
2.1.4 Radiological Protection for the Public ............................................................................. 112
2.1.5 Radiation Emergency Preparedness ................................................................................ 113
2.2 Radiation Safety Management in Research Reactor .......................................................... 113
2.2.1 Introduction ...................................................................................................................... 113
2.2.2 RTP Technical Specifications........................................................................................... 113
2.2.3 Safety Objective ............................................................................................................... 114
2.2.4 Organisation and Management of Safety ........................................................................ 114
2.2.5 Safety Analysis Report ..................................................................................................... 115
2.2.6 Quality Assurance Programme ........................................................................................ 116
2.2.7 Radiation Protection Programme..................................................................................... 116
2.2.8 Emergency Preparedness and Response.......................................................................... 116
2.2.9 Operation and Maintenance ............................................................................................. 117
2.2.10 Reactor operation supervisors, radiation protection supervisors and trainees .............. 117
2.2.11 Regulations and Licensing ............................................................................................. 117
2.2.12 Peer Review.................................................................................................................... 117
2.3 Radiation Safety Management in Radioactive Waste Management .................................. 118
2.4 Radiation Safety Management in Transport of Radioactive Material ...............................120

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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,
the Atomic Energy Licensing Bill was drafted and was passed by Parliament in April 1984 as
the Atomic Energy Licensing Act (Act 304).
Figure 1: Hierarchy of Legal System

There are three main regulations made under the Act 304 namely:
Radiation Protection (Licensing) Regulations 1986;
Radiation Protection (Transport) Regulations 1989
Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010;
Atomic Energy Licensing (Radioactive Waste Management) Regulations 2011
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
was placed 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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






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 ;andTo 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 the jurisdiction of the 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 of specialists and workers involved with radiation related industry
are maintained by the AELB and MOH. However, the exact total number of workers involved
with radiation is very difficult to estimate.
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
shall be provided with 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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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 that include including generalradiation awareness, radiation protection, use of radionuclides, use of gauges, transport, and useof radiation in medical procedures.
1.4 Standardization on radiation and radioactivity
1.4.1 External radiation andpersonnel 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 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
dosimeters or 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 are normally used for determination of the output of Cobalt-60 teletherapy units andmedical linear accelerators (linacs) should be calibrated in terms of exposure, air kerma or
absorbed dose to water. Radiation measuring instruments need to be calibrated to ensure thatthey give accurate and correct reading with a certain uncertainty and to comply with theregulations imposed by the relevant authority. They should be calibrated annually or after major
repair. In Malaysia, calibration of radiation measuring instruments is a legal requirement underthe Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010. The
SSDL-Nuklear Malaysia was established 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 in radiation dosimetry in the country. It is also the national focal
point for the calibration of radiation measuring instruments used in radiation protection andradiotherapy. More than 1500 radiation instruments are normally calibrated every year. The
laboratory has also the responsibility to ensure that the calibration services provided ollow
internationally accepted metrological standards. This is achieved by calibrating the protection
and therapy level dosimeters that belong to SSDL-Nuklear Malaysia against the PrimaryStandard Dosimetry Laboratories (PSDLs) or the International Atomic Energy Agency (IAEA)
or by participating in the international 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 of106

FNCA Consolidated Report on Radiation Safety (Malaysia)

the 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 thestaff 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 radioactive and x-ray sources that areoperated remotely in the control room. This room also contains monitors coupled to video
cameras in the irradiation rooms. The rooms are provided with calibration benches running ona 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 orlaser. Laser alignments are also installed at each irradiation room to ensure that the radiation
survey meters and dosimeters are placed in the centre of the radiation beam during themeasurements. The irradiation rooms are also provided with appropriate safety equipment andaccessories 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 wereselected to match the beam qualities offered by the International Bureau of Weight and
Measures (BIPM) and based on 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 the calibration of radiation protection instruments. Theirbeam 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 for calibration 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

107

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 withdifferent activities 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 and60
Co gamma sources with activities 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 toprovide national standards for air kerma and absorbed dose to water at therapy level andcalibration 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 and 38 Gy/s. The irradiation procedure is controlled by a personal computer which

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stores the calibration data for the source used. The specifications of beta sources are
summarized in 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 andmanufactured by PTW, Germany and the Austrian Research Centre, Austria, respectively. The
chambers are calibrated 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 ionization chamber NE 2571 has been selected as reference chamber for thecalibration 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
traceable to the National Metrology Laboratory, SIRIM Berhad. The leakage current for thesystem ionization chamber plus electrometer is considered negligible. The stability of thechamber plus electrometer system is checked at regular intervals using a 90Sr and 241Am checksource. Working standard dosimeters used for protection and therapy levels at SSDL arecalibrated against secondary standard dosimeters. They are routinely used for the calibration ofradiation 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

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FNCA Consolidated Report on Radiation Safety (Malaysia)

survey instruments and for determination of their energy response. For the x and gamma
radiation qualities, the conversion coefficients given in ISO Standard 4037-3 were used forconversion from air 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 andrelative 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 radiation, respectively.
Calibrations are performed either by the substitution method (comparing the response of the
instrument to be calibrated with that of a reference standard instrument) or simultaneous
method (both instrument to be calibrated and reference standard instrument are placed in theradiation beam at the same time and irradiated together). 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 are calibrated 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 particular distances of each sources i.e. 90Sr/90Y, 85Kr and147
Pm have been determined by the PTB, the national standard laboratory of Germany or byusing PTW extrapolation ionization chamber. Portable survey instruments are calibrated atleast at one point on each measuring range i.e. at approximately half of their full scale value orin each decade for an instrument with a logarithmic scale or with digital indication. The
calibration factor or coefficient is defined as the ratio of the value of stated true exposure ordose 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 towater calibration coefficient, ND,W at a single high energy photon beam which is normallyreferred 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 wasperpendicular 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 thechamber distance (FCD) is 100 cm and the field size diameter ( ) is 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) producedin the chamber under calibration. The charge is measured by the electrometer which belongs to
the users. The results of the calibration is normalized to the standard atmospheric conditions(i.e. T = 20 OC, P = 1013.25 mbar and R.H. = 50%). The calibration is performed by thesubstitution method using the SSDL reference standard chamber.

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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
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 ofionizing 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, license conditions, code of practice, and guidelines,
established under the Act 304 and regulatory directive published by the AELB from time to
time.
These include all radiation management considerations for research, industrial and medical
related facilities as follows: Radiation Protection (Licensing) Regulations 1986
 Radiation Protection (Transport) Regulations 1989;
 Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010;
 Atomic Energy Licensing (Radioactive Waste Management) Regulations 2011;
 Guideline 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.
 Guideline on Preparation and Exercises of Nuclear and Radiological Emergency Plan Guideline to conduct leak test for sealed source Guideline on Preparation of Security Plan for Radioactive Source Guideline for HS Code: Strategic Item Under Strategic Trade Act 2010 (Act 708)
 Recognition and Duty of Radiation Protection Adviser (RPA) Duties and Responsibilities of Radioactive Materials Carrier.
 Guideline 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
 Guideline on Radiological Monitoring for Oil and Gas Facilities Operators Associatedwith Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM)’
 Guidance on Scheme Towards the Recognition of a Radioactive Laboratory by Atomic
Energy Licensing Board.

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FNCA Consolidated Report on Radiation Safety (Malaysia)

Guideline for Decommissioning of Facilities Contaminated with Radioactive Materials.
Guideline on Preparation of Radiation Protection Programme

2.1.2 Radiological Protection for Radiation Workers
It has been recognised that exposure to a certain level can cause clinical damage to human tissues.
It is therefore essential that activities involving radiation exposure shall be subjected to certain
standards of safety in order to protect individual worker exposed to radiation. As such, all radiationindustries and facilities are required to implement ALARA concept limits that will lead to detrimental
effects arising from occupational 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 the 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 are be controlled in accordancewith the requirement of the regulations and guideline.
The licensee is also responsible for ensuring that the optimization process for measures to112

FNCA Consolidated Report on Radiation Safety (Malaysia)

control discharge of radioactive substances to the environment comply with the requirement of
the regulatory body taking into account exposure pathways, changes in the habitats 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 must also be provided withadequate information and instruction before they enter a controlled area to ensure appropriate
their protection
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 the obligation of theoperator to establish radiological emergency 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
is a national, state or district level, if the emergency is considered a disaster. The AELB is thelead technical agency while Nuclear Malaysia will provide the technical assistance during
emergency, if necessary. In the event of a radiological emergency the following plans are inplace:
 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, isan 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
TRIGA PUSPATI (RTP), was built. It came into operation in 1982 and reached its firstcriticality on 28 June 1982.
The reactor was designed to effectively implement the various fields of basic nuclear
science and 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 andagricultural purposes, neutron radiography and Small Angel Neutron Scattering (SANS).
2.2.2 RTP Technical Specifications
RTP was supplied by General Atomic of the USA and installation programme was started on 9
November 1981. RTP is a pool type reactor where the reactor core sits at the bottom of 7 metrehigh aluminium tank which is surrounded by a biological shielding made of high density
concrete (see Figure 2). The reactor uses solid fuel elements in which a zirconium-hydride113

FNCA Consolidated Report on Radiation Safety (Malaysia)

moderator is homogeneously combined withenriched uranium. Demineralised water acts
both as coolant and neutron moderator, whilegraphite acts as reflector. The following arebrief descriptions of RTP:






Type: TRIGA Mk II, pool type
Fuel: Uranium Zirconium Hydride
Alloy
Coolant: Light Water
Moderator: Light Water
Reflector:Graphite






Control Rods: Boron Carbide
Figure 2: Nuclear Malaysia’s Reactor TRIGA PUSPATI
Status: Operating
Operational Mode: Steady State (1MW)
Operation: 6hrs/day weekdays

2.2.3 Safety Objective
Since its establishment, the safety of RTP operation is a prime concern of the management
and staff of Nuclear Malaysia. These safety considerations include during operation, repair
and maintenance, 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 be 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 which is esponsible for the promotion, development andapplication of nuclear technology and nuclear related technology for the national development,
is committed to continually improve and prevent pollution, incidents, accidents andoccupational illness in its operation. This is the commitment of the management in ensuringsafety at Nuclear Malaysia complex. Towards this end, Nuclear Malaysia will: Comply with all applicable environmental, occupational safety and health, legal andother requirements.
 Minimize release of pollutants to air, water, land and promote waste minimization
through reduction, 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.

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 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 thatmanagement 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.

Figure 3: RTP Safety Management System

For RTP, the set-up of organization safety management is shown in Figure 3. The RTP isheaded by a Reactor Manager who irectly reports to the Director of Nuclear Power. To
maintain high level of safety, the operation and maintenance of RTP are supported by othergroups 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

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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 approval. In preparing this document, Nuclear
Malaysia had engaged experts from abroad to help prepare the document due to lackcapability and expertise to conduct 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 in 2013 and will be submitted to the regulatory body this year for comment. Someof the contents of the QAP are Operational Control, Emergency Response and Preparedness,
Safety and Health, Physical Security, Infrastructure Maintenance, Reactor Maintenance,
Experiment and Modification, Measurement and Monitoring Device Control, Human Resource
Management, Waste Management, Special Nuclear Material Counting Control and refueling.
2.2.7 Radiation Protection Programme
Radiation exposure is set-out in the safety manual approved by the SHE-MS Committee. It
is based on the Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010
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 most 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 three years.
Environmental samples such as water, sediments, soils, vegetables from areas surrounding
Nuclear Malaysia complex are collected and analysed. External radiations from the nuclear
installation are monitored using TLDs which are changed on a monthly basis.
2.2.8 Emergency Preparedness and Response
Emergency preparedness means being ready to react or respond 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
are very concern about emergencies arising from malicious use of radioactive material or ‘dirty
bomb’.
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 has been recently
revised. 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
twice a year.

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2.2.9 Operation and MaintenanceWithout a doubt, a good design, manufacture and construction of reactor are pre-requisites
for high levels of safety. However, the ultimate responsibility for safe operation lies with theoperating organization (Safety Principles 1). Therefore, Nuclear Malaysia is really emphasizedon this issue. RTP reactor building, equipment and facilities are well maintained, generally clean
and tidy and in good condition. The annual and semi-annual maintenance are carried out in Juneand December, respectively. Any change in operation and maintenance plan must be approvedby the Reactor 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 new staff, they are required toattend an induction course while the existing staff are encouraged to attend a radiation safety
awareness training course conducted by Nuclear Malaysia. Nuclear Malaysia also sends theirstaff to, either local institutions or a broad for updating their skills and knowledge.
For a reactor operator, a training programme which is based on the guidelines issued by the
AELB is conducted by Nuclear Malaysia while the examination and issuance of operator
license are managed by the AELB in accordance with a guidelines on Standards for
Certification and Recertification of Research Reactor Operator (LEM/TEK/54). The reactor
operator license can only be renewed after the licensed operators have successfully undergone arefresher 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,
to maintain independency, Nuclear Malaysia is licensed by the Atomic Energy Licensing
Board (AELB), which is an independent body established under the Atomic Energy Licensing
Board 1984 (Act 304). This is to ensure that the safety is kept in high standards 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 being complied with.
Alongside inspections, yearly dialogue and direct meeting between the Nuclear Malaysia
and AELB are made to exchange information and resolution on 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 safetyin accordance with 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
culture. For this purpose, international peer review group on safety culture and nuclear safety
are welcome. In 2005, the implementation of nuclear safety culture at RTP has been reviewed
by Forum for Nuclear Cooperation in Asia (FNCA) review team. Recommendations from thisteam have been implemented.

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2.3 Radiation Safety Management in Radioactive Waste Management
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 is also 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 Technology Development Centre (WasTeC), an organization within Nuclear Malaysia, isgive responsibility to manage radioactive waste and chemical waste. WasTeC is recognized as anational centre for management of radioactive waste in Malaysia. In this centre, radioactive
wastes are categorized and separated based on their types, solid or/and liquid according to thestandard classification of radioactive waste established by the AELB in the Atomic Energy
Licensing (Radioactive Waste Management) Regulations 2011. Radioactive waste in Malaysia isclassified in accordance with the above regulation.
Table 1: Classification of radioactive waste according to the Atomic Energy Licensing(Radioactive Waste Management) Regulations 2011

There are various facilities available for managing the various types of waste received by the
WasTeC. Facilities that are available at WasTeC include: Low-Level Effluent Treatment Plant (LLETP) - The treatment of mainly low-level aqueous
liquid waste is by chemical process (coagulation-flocculation). Compartments are alsoavailable for handling and storage of liquid organic waste on mild steel racks (Fig. 4).
 Laundry facility - two heavy-duty washing machines, one dryer, one unit press-ironing
equipment
 Laboratory for analysis and research - related equipment for necessary effluent analysis andresearch work. Gross beta-gamma counter and gamma spectrometer Solid waste processing area - Solid wastes are collected, segregated, decay storage is applied
where possible and further treatment done accordingly - including cementation and118

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compaction. A segregation cabinet is available for waste segregation.
 Decontamination area
 Conditioning area - conditioning of waste including spent sealed sources in cement matrix isdone using a batch cement mixer. Currently, only 200-liter steel drums are used in theconditioning process.
 Waste Compactor - an in-drum compactor for volume reduction of solid waste in 200-liter
drum was acquired in the first quarter of 2000.
 Transport - a vehicle for transporting waste Waste Storage Facility - a pretreatment storage facility and an interim long-term storage
facility are available at the center. The construction of the long-term storage facility wascompleted in August 2000. The facility was designed to accommodate 2,400 drums of
200-liter waste package after treatment and immobilization. Stacking of the drums is limited
to three drums high - and further expansion of storage area is possible

Figure 4: Low level effluent treatment plant

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Currently Nuclear Malaysia has no spent fuel at all. However, the RTP was designed in sucha way that it can be used as a storage facility for spent fuels before these spent fuels are sent
back to the supplier.

Figure 5: In-drum Compactor

2.4 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 framework of Malaysia currently applies 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 transportationof radioactive materials in Malaysia whether they transport by air, water-ways or inland (roadand railways). 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 the transport regulation.
In 1996, 2003, 2005 and 2012, the IAEA published revisions of their regulations for the safe
transport of radioactive material and recommended that adoption of these revised regulations inmember states to achieve worldwide harmonization of their application. However, in Malaysia,
since gazetted in 1989, the transport regulation has never been 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 regulation and the new amended regulation is
waiting to be gazetted.

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8. Mongolia
Part 1. Radiation Safety in Radioisotope Facilities...........................................................................122
1.1 General ................................................................................................................................122
1.1.1 Legal and Regulatory Infrastructure ................................................................................122
1.1.2 Emergency planning and response ..................................................................................126
1.1.3 Control of orphan source..................................................................................................127
1.1.4 Strengthening of export import control............................................................................127
1.1.5 Ocupational exposure control ..........................................................................................128
1.1.6 Public exposure control ....................................................................................................128
1.2 National Waste Management Policy and Strategy .............................................................130
1.2.1 Source of radioactive waste .............................................................................................130
1.2.2 Long-term storage facility for spent or disused sources ..................................................131
1.2.3. NORM residue management ..........................................................................................131
1.2.4 Clearance Regime for Radioactive Waste .......................................................................131
1.2.5 Disposal of Radioactive Waste ........................................................................................131
1.2.6 Decommissioning of Nuclear and other Facilities Containing Radioactive Materials ..131
1.2.7 Remediation .....................................................................................................................131

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8. Mongolia
Part 1. Radiation Safety in Radioisotope Facilities
1.1 General
Mongolia is a landlocked country
in Northern Asia between Russia andChina with a population of 2.9 million
and an area of 1.5641 million square
kilometers. It is one of the least
densely populated countries in theworld.
Mongolia became a Member Stateof the IAEA in 1973 and is a memberof FAO, ILO and WHO.
Figure 1: Map of Mongolia

1.1.1 Legal and Regulatory Infrastructure

1.1.1.1 Mongolia's nuclear weapon - free status
Mongolia declared itself a nuclear-weapon-free zone in 1992. This self-declared status
has been recognized internationally through the adoption of UN General Assembly
resolution 55/33S on “Mongolia's international security and nuclear weapon free status. A
law was also enacted in Mongolia to institutionalize this nuclear-weapon-free status.
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 Agreements:
 Agreement on the Privileges and Immunities of the IAEA
 Convention on the Physical Protection of Nuclear Material
 Convention on Early Notification of a Nuclear Accident
 Convention on Assistance in the Case of a Nuclear Accident or Radiological
Emergency
 Revised Supplementary Agreement Concerning the Provision of Technical Assistanceby the IAEA (RSA) Third Agreement to Extend the 1987 Regional Co-operative Agreement for Research,
Development and Training Related to Nuclear Science and Technology (RCA) Application of safeguards in connection with the Treaty on Non-Proliferation of
Nuclear Weapons (with Protocol)
 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
Mongolia is currently considering joining the Convention on Nuclear Safety and Joint
Convention on the Safety of Spent Fuel Management and 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. In the next few years it
is possible that current uranium exploration and development in Mongolia will progress tooperational mining. This might include the re-establishment of open-cut and undergroundmining, and the development of new in-situ recovery (ISR) acid leach mines.
The Nuclear Energy Agency (NEA) is responsible for all aspects of uranium mining
including exploration, mine/mill construction and operation, radiation protection,
environmental protection, transport, decommissioning and remediation. Mongolia has not
yet develop the regulation for uranium mining and processing.
1.1.1.4 Legislative Framework
The Parliament of Mongolia has passed the Nuclear Energy Law, which entered into force
in August, 2009. The law on Radiation Protection and Safety was repealed on 15 August 2009.
The Nuclear Energy Law now regulates both nuclear and radiation safety issues. The powers
and activities of the Nuclear Energy Agency and its regulatory functions is described in the
Nuclear Energy Law. The relevant guides and regulations within this legislative frameworkare: Radiation Safety Standard (1983)
 Basic Regulation on Radiation Sanitation (1983)
 Transport Regulation for Radioactive Sources (1987)
Draft of updated regulations for IAEA BSS conformity has been prepared.
 Mongolian National Standard. MNS 6240-2011. Technical Requirements for the
Packaging of Radioactive material /Updated by the IAEA Regulation (1996)
 Radiation Safety Regulation on Diagnostic Radiology (2011)
 Safety Regulation for the Use of Density/Moisture Gauges in Road and Dam
Construction (2011) The dose limits in the Radiation Safety Standard (1983) have been superseded by the
Mongolian National Standard MNS 5631:2006 and MNS 5630:2006.
NEA has also developed the NORM Regulations for Oil-Gas Industry, and is now awaiting
Government approval. Safety regulations for Uranium Exploration and Processing are indevelopment stage. Security regulation for radiation sources was drafted in 2013.
1.1.1.5 Regulatory body and its functions
Mongolia has participated in activities of IAEA Inter-Regional Model Project INT/9/143
since June 1996. Under this project Mongolia has made good progress in the establishment of
an independent regulatory body and in the obtaining of Parliament approval of the first law on
Radiation Protection and Safety.
The Nuclear Regulatory Authority (NRA) was established as the Regulatory Body inMongolia by Governmental Resolution No 180 on 13 August 1997 under the Nuclear Energy
Commission (NEC) of the Government of Mongolia. It has since been restructured under theState Specialized Inspection Agency (SSIA) during 2003-2005 to be an independent regulatory
body separated from promotional activities. However the status of NRA within the SSIA was123

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not very effective nor competent.
In January 2009, the Nuclear Energy Agency (NEA) was established under the competenceof the Prime Minister to serve as the government regulatory agency by the Government
Resolution No.64 (24 Dec 2008) “Establishing Regulatory and Implementing Agency of theGovernment”. In this Government decision, the regulatory body NRA was separated from
SSIA and incorporated into NEA as the Nuclear and Radiation Regulatory Authority (NRRA) .
Parliament Decision No.45 of 2009 adopted State Policy of Mongolia on the Exploitationof Radioactive Minerals and Nuclear Energy.
The Governmental Regulatory Agency - Nuclear Energy Agency (NEA) under the Prime
Minister is responsible for development of policy for the activities related to the developmentof nuclear research and technology, radiation protection and nuclear safety, use of radiation
sources and coordination of uranium mining activity with other relevant organizations.
NEA has the following departments:
 Administration
 Nuclear Technology Authority
 Nuclear and Radiation Regulatory Authority (NRRA).
ORGANIZATIONALSTRUCTURE
OFofNUCLEAR
ENERGYAGENCY
Figure 2: Organizational
Structure
Nuclear Energy
Agency(NEA)

NRRA operates as the regulatory body responsible for the implementation of regulatory
functions of the NEA as described in the Nuclear Energy Law.

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 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 to authorization which commensurates with the potential magnitude and natureof the hazard presented by the practices, including separate requirements for registrationand licensing.
 Inspection
The NRRA has established a planned and systematic inspection program. The
inspection frequency depends on the risks and results of previous inspection findings. It
includes planned, announced and unplanned, unannounced and follow-up inspections
carried out in accordance with 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 the
responsibility to be assumed by violator of any nuclear energy legislation.
The enforcement policy has been established in the NEA procedure. This policy provides
for a range of sanctions commensurate with the seriousness of the non-compliance. The
NEA has also established formal arrangements with relevant government agencies where
enforcement requires the involvement of the police, ministry of justice or other authorities.
The Nuclear Energy Law and the Law on Inspection empower inspectors to takeon-the-spot enforcement actions.
1.1.1.6. Inventory of Radiation Sources
The NRRA of NEA registers all identified sources, irrespective of whether they fall underthe exemption category. It has a complete inventory of all radiation sources and it has acentralized database for all identified facilities and sources in the country. Regulatory
information including source and facility data stored in Regulatory Authority Information
System (RAIS) software and the hard copy versions in parallel. Small calibration sources werealso registered. The inventory is updated with information from inspection findings as well asfrom 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

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Table 1: Radiation Facilities and Radiation Sources

Facilities

No. of organizations/No. of units

Research Reactor0

Isotopes Production

0

Synchrotron

0

Research Gamma Irradiator

1 unit /27 sources

Industrial Gamma Irradiator

0Gamma Tele-therapy

1hospital/2 units

X-ray devices- Diagnosis and Therapy in medicine

157 hospitals/332 units

X-ray devices – Industry

1

Linear accelerator (LINAC)

0

Medical Brachytherapy

1

Level/density thickness or conveyor gauge

7 company/191 units

Density/moisture gauge

10 company/21units

Industrial Radiography

4/7

Education and Research Laboratories

20 organizations/149 sources

PET cyclotron

0Electron beam ( education)

1

Electron beam ( Irradiator)0

Neutron Generator

1

Radioactive Waste Storage Facility (Long term storage)
Well logging

1 center
23 company/82 units

Veterinary X ray device

2

X ray scanners for customs and security control
X ray analysers

34/88 units
21

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 NEMA received training abroad in radiation emergency

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planning, preparedness and response. A general law requires users of radiation sources to notify
NEA and NEMA in the event of an emergency and an accident.
1.1.3 Control of orphan source
An inquiry into what effort, if any, was made to determine if there were abandoned sourcesin Mongolia. Source abandonment may be due to industrial economic disruptions, transition
from centralized to market economy or government changes of the 1990’s. By working closelywith potential users of radiation sources (survey through a system of notification), about 20
orphan sources are identified and secured during 1995-2008 with cooperation from authorizedusers and other relevant Agencies. Mongolia’s law and regulations stipulates that all orphan or
abandoned radiation sources must be secured and stored at the Isotope office without any
charge.
Requirements on reporting loss of control and to encourage awareness of, and monitoring todetect, 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 acountry with this geography and a small population, border management is becoming a serious
challenge at a time of increased concerns over trans-national crimes, including trafficking of
nuclear-related items. Mongolia’s efforts to respond to the threat of nuclear smuggling havebeen beset by a shortage of trained personnel and necessary equipment.
Mongolia has decided to focus on developing effective border controls to detectcross-border smuggling of nuclear-related items in light of the adoption of United Nations
Security Council Resolution 1540.
Under the Memo of Understanding, the US Department of Energy is providing Mongolia
technical assistance in the form of equipment, materials and training for use at border ports forthe purpose of detecting and interdicting illicit trafficking of special nuclear material and otherradioactive material. The deployment is being carried out under its Second Line of Defense
Program. A total of 83 radiation portal monitors for gamma/neutron detection have been
installed at 15 main border ports for passenger, vehicle and rail monitoring as of 2013.

Figure 3: Gamma/neutron detection at the border ports for passenger, vehicle and rail monitoring127

FNCA Consolidated Report on Radiation Safety (Mongolia)

1.1.5 Occupational exposure control (Monitoring for radiation workers)
NEA provides:
 Occupational exposure control (external exposure only) About 1235 radiation workers from 161 organizations are under the regular personal
dosimetry control as of 2013 (95%)
Figure 4: Occupational Exposure Control
Radiation Workers in Different Practice

Figure 5: Number of Radiation Workers

Weaknesses:
 Internal dosimetry is not yet established Personal monitoring for radon and neutron are not yet available
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. There is need tostrengthen the environmental monitoring network to ensure emergency preparedness.
Air fallout samples for gross beta measurement are collected in 23 local stations. Aerosol
gross beta activity measurement are carried out 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 meteorologicalcentre in Ulaanbaatar three times a month. NEA submitted a Project Proposal for the
Establishment of an Online Environmental Radiation Monitoring Network in 2011 to theGovernment for approval.
Due to the large scale nuclear weapons testing programs in 1970 near Mongolia’s borders,the environmental monitoring program in these regions was focused on the analysis of air,water and soil samples. There is an urgent need for more enhanced measurements for alphaand beta contamination.

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It is very important to develop an online environmental monitoring network for Mongolia
given its geographical location between two nuclear countries and also for emergency response
planning purposes. NEA has prepared a project proposal to establish an effective andinternationally compatible national capabilities in preparedness, timely response to potential
damages against global fallout, occupational hazard in the mining industry and effective
protection of environment, homeland and social securities. This proposal was submitted to theGovernment for approval in 2012.

System Configuration
for Full-scale
Regulation
Figure 6: System Configuration
for Full-scale
Regulation• Full configuration• Satisfaction of national needs• Full-scale regulation

Authorities
Release of Alarm

Communication Provider

INTERNET

FirewallApplication Server

DB Server

Data Server

Web Server (MS IIS)MS SQL Server

Redundant

Early Warning
Environmental Radiation
Monitoring Network

MODEM• Nationwide monitoring posts• Network system with auto polling system• Data acquisition unit
• Centralized data display unit
• DB for external access of the data

GSM /GPRS

MODEM
17

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 andcontrols appear to have been established by the Regulatory Body.
The food samples are initially screened with a food contamination monitor (Berthold
LB200) measuring gross gamma activity. Food samples showing unreasonably high gross
gamma activity are measured again with a high-resolution HPGe gamma spectrometer.
Between 1000-2000 samples of domestic and imported foodstuffs are monitored forradionuclide contamination by the Radiation Laboratory of NRRA of NEA annually. In
addition, Ulaanbaatar city tap water is monitored daily, and water samples from 8 other regions
are regularly monitored.

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1.1.6.3 Control of Chronic Exposures
Mining is one of main economy sector in Mongolia. There are 65 coal mines/deposits, 22
mines of other mineral resources and 144 building material factories under the regularsampling program by the regulatory body.
Regulatory control of NORM in workplaces other than uranium projects is not in place due
to shortage of manpower, resources and analytical capabilities. NORM in these workplaces is
not regulated by any legislation.
Potential chronic exposure scenarios have been identified in the country but they are notsufficiently characterized. NORM generating industries in the country have not been fully
identified.
There is an urgent need for continuing indoor radon measurements due to the extensive useof coal ash as a building material. Radiation Laboratory provides limited service fordetermination of radon 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 process
scrap metals. Portal monitors were used to detect the presence of significant amounts ofradioactive substances in materials going for recycling.
As the scrap metal dealers do not have their own radioactivity monitoring equipment,
China has requested NRRA to provide Radiation Certificate for all scrap metals exported toChina by rail. NRA fulfils this condition by measuring the scrap metal with monitors when it isbeing loaded onto the railcars.
Radiation Portal Monitors installed at main Port of Entries (PoE), including the entry/exit
points for rail and road have proven to be very useful in the detection of any orphan sourcesin materials for recycling and screening for radioactivity in materials at each PoE.
1.2 National Waste Management Policy and Strategy
Mongolia’s national radioactive waste management strategy described under the Exploitationof Radioactive Minerals and Nuclear Energy has been approved in the Parliament Decision
No.45 (2009). A Waste Management Program for Mongolia has been drafted but not yet
approved by the Government. Draft regulations for waste management and safety are 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,
have very short half-life. When the activity of liquid waste falls below the IAEA clearance level,
it is discharged 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
problem, but the situation could change with the development of new phosphate, oil, gas anduranium industries.

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1.2.2 Long-term storage facility for spent or disused sources
The Isotope Centre of the NEA has a national long term waste storage facility located about
20 km from Ulaanbaatar in Mongolia. NEA has taken considerable measures in upgrading thephysical protection features of the Isotope Centre since 2008. This facility has a camera
surveillance system and is under security guard for 24 hours a day.
Mongolia has no disposal facilities for these sources. NEA has a long-term plan to convert
this storage facility into a disposal facility. Due to the small quantity of radioactive waste in
Mongolia, waste processing is not carried out on a regular basis. There is also no procedure inplace for the characterization and segregation of radioactive waste. Several Co-60 sources of
disused irradiator are stored in the Institute of Physics and Technology of the Academy of
Sciences. Radionuclides use in nuclear medicine and radio-immunoassay (I-131, Tc-99m and
I-125) are decayed in storage.
1.2.3. NORM residue management
NORM workplaces are not identified and there is strong need to establish a regulatory
criteria for the uranium industry as well as other NORM residues-generating activities in
Mongolia.
There are no special regulations for waste management in the uranium industry and NORM
workplaces, however appropriate international standards are applied for safety assessment andenforcement.
1.2.4 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.
Liquid waste, generated from nuclear medicine hospitals, has a very short half-life. Whenthe activity of liquid waste falls below the IAEA clearance level, it is discharged into thesewerage system.
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.
The Isotope Centre had a small burial area where contaminated material from a previous Sr-90
incident was buried in 1993. This is covered in a brief report submitted to the IAEA.
1.2.6 Decommissioning of Nuclear and other Facilities Containing Radioactive Materials
As there is no national waste management policy and strategy, the funding mechanisms fordecommissioning need to be addressed.
There are no plans for the shutdown and decommissioning of any nuclear and other facilities.
However the research irradiator from the Institute of Physics and Technology is in need ofdecommissioning.
Recently, the Nuclear Research Centre of the National University of Mongolia requested
assistance for the decommissioning of a neutron generator. The neutron generator, which has
been out of service for 15 years, was made in the former USSR and was used for research andtraining.
1.2.7 Remediation
Mongolia needs to carry out uranium ore remediation near the former Mardai Uranium
Mine which is located in the Dornod province,,situated on the eastern part of Mongolia. The

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Radiation Laboratory of the NRRA performs environmental monitoring measurements in order
to assess the potential risk from the tailings pile at the former uranium mines.
IAEA TC Project on Environmental Impact Assessment and Remediation of the Uranium
Mining Legacy MON/9/005 has been implemented by the Ministry of Environment and the
NEA since 2005 and was completed in 2010. IAEA experts had visited this legacy site under the
project.
1.2.8. Education and training
Education and training on radiation protection in Mongolia includes:• Internal education and training• International workshops and meetings on nuclear and radiation safety• Programs for multilateral cooperation- IAEA long- and short-term training courses- International long- and short-term training courses
The Nuclear Research Centre of the National University of Mongolia provides Bachelor andMaster degree education on nuclear physics and nuclear technology. University of Science andTechnology contributes in education of engineering on non-destructive testing (NDT) andmining practices. Currently, there is no specific education system on radiation protection or
health physics in Mongolia. Regulatory staff training has been provided by IAEA as well as via
other bilateral cooperation programs.
Radiation protection training for radiation users poses some difficulties in Mongolia due tothe lack of service providers. The Regulatory Body has provided limited training to radiation
users over the last several years. Since 2013, some non-governmental organisations such as the
Mongolian Radiation Protection Society (MRPS) has been established, providing radiation
safety and protection training to the users,
1.2.9. Calibration of Monitoring Equipment for External Radiation
Dosimetry Calibration Laboratory was established in 1998 and is responsible for thecalibration of gamma radiation protection monitoring instruments. This is the only laboratory inthe country operating as the national laboratory for radiation standards and calibration ofradiation monitoring instruments. Secondary standard dose meter and chambers have beencalibrated against the IAEA standards which are traceable to primary standards. The Laboratory
was accredited in December 2010 by the Mongolian Agency for Standardization and Metrology.


Equipment and facilities for calibration
Dosimetry Calibration Laboratory has facilities to calibrate radiation instruments anddevices for photon energies between 662keV and 1250keV.
 QA/QC program and Performance of Equipment
Reference instruments with chambers have been calibrated against the IAEA standards at
the IAEA dosimetry laboratory in October 2010. Regular performance tests and stability
checks for instruments with chambers are done to ensure the accuracy and reliability ofthese reference instruments. Percentage of deviation of the stability check source for thetherapy chamber is maintained within +/-0.5 and protection level of +/-1. All electrometerand chambers are kept in a dry cabinet when not in use. Decay correction is applied to all
the data at calibration.

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1.3 Future goals and priorities
 Strengthening of regulatory infrastructure and regulatory control of radioactive materials;
 Revision of legislations and developing regulations for different practices; Implementation of an effective system for detecting and preventing illicit trafficking of
nuclear and radioactive material; Strengthening of radiological emergency response and planning at national level; Upgrading of Environmental Monitoring capabilities and Radiation Protection Technicalservices Establishment of internal dosimetry control and nationwide radon survey
 Strengthening of radioactive waste storage facility and establishment of disposal facility
 Upgrade the emergency preparedness and response capability in the country
 Establishment of education and training system on radiation protection

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9. The Philippines
Part 1. Radiation Safety in Radioisotope Facilities .................................................................. 135
1.1General .......................................................................................................................... 135
1.1.1 Legislative Framework and Policy for Radiation Safety......................................... 135
1.1.2 Structure and System (Regulatory Organization) .................................................... 135
1.2 Outline of Radiation Facilities and Radiation sources ...................................... 136
1.2.1 Number of Specialists and Workers in Related Organizations................................ 136
1.2.2 Number of Radiation Facilities including Related Facilities................................... 136
1.2.3 Future Plans and Issues to be Resolved ................................................................... 139
1.3 Education and Training................................................................................................ 140
1.3.1 Radioisotope usage ................................................................................................... 140
1.3.2 Radiological Protection ............................................................................................ 141
Part 2. Status of Radiation Safety Management .................................................................... 141
2.1 Radiation Safety Management System ....................................................................... 141
2.2 Radiological Protection for Radiation Workers .......................................................... 143
2.3 Radiological Protection for Radiation Area ................................................................ 143
2.4 Radiological Protection for the Public ........................................................................ 143
2.5 Radiation Emergency Preparedness ............................................................................ 144
2.6 Radiation Safety Management in Research Reactors ................................................. 145
2.6.1 Radiation Safety Management System .................................................................... 145
2.7 Radiation Safety in Radioactive Waste Management ................................................. 147
2.7.1 Radiation Safety Management System .................................................................... 147
2.7.2 Criteria to define Waste Category ...................................................................... 147
2.7.3 Managing sources at the end of their life cycles .............................................. 148

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9. The Philippines
Part 1. Radiation Safety in Radioisotope Facilities
1.1 General
The Philippine Nuclear Research Institute (PNRI) was formed from the previous agency, thePhilippine Atomic Energy Commission (PAEC) when the then Philippine President re-organized
the Department of Science and Technology (DOST) in early 1987. In this reorganization, the
PAEC was transferred from National Science and Technology Authority (NSTA) to DOST andwas re-organized to become the PNRI. PNRI retains both the promotional mandate andregulatory powers and authorities of PAEC.
Cognizant of the need to update existing laws governing the peaceful use of atomic energy inthe country, a new law has been drafted and is currently undergoing the legislative mill process.
The proposed Act aims to rationalize and strengthen the regulatory powers of the Philippines
over Nuclear Energy Facilities and the Peaceful Applications of Ionizing Radiation Sources thru
the creation of the Philippine Nuclear and Radiation Safety Commission. The law will basicallyaddress the need to have an independent regulatory body for all nuclear matters in the country.
This will ensure that the Philippine national legislative and regulatory framework is consistent
with the nation’s obligations under relevant international instruments and that it provides anadequate basis for further development of nuclear technology for peaceful purposes.
1.1.1 Legislative Framework and Policy for Radiation Safety
The Philippines legislative framework on radiation safety includes a hierarchy of laws,
executive orders and regulations under the National Constitution. The Science Act of 1958
(Republic Act of 2067) created the PAEC, the predecessor of the now PNRI, was mandated topromote the peaceful uses of atomic energy and promulgate rules and regulations to ensure thesafe use and application of radioactive 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, Presidential Decree (PD) 480 (1974), as amended by PD 1372, Executive Order(EO) 119 and EO 102 established the Department of Health (DOH) as the Regulatory Authority
for the regulation of X-ray units and other electronically generated radiation devices, including
non-ionizing radiation.
1.1.2 Structure and System (Regulatory Organization)
The regulatory framework considers nuclear facilities and radioactive materials separatelyfrom radiation emitting devices, with separate jurisdictions for each. The PNRI through its
Nuclear Regulatory Division (NRD) regulates the former, while the DOH through its Food andDrugs Administration’s (FDA) Center for Device Regulation, Radiation Health and Research
regulates the latter (CDRRHR).
The PNRI has the roles of promoting nuclear science and technology, providing services,and regulating the peaceful application of nuclear and radioactive materials. 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 NRD of PNRI the authority and responsibility of regulatory

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control over PNRI radiation facilities and research laboratories. An Office Order signed by the
PNRI Director in 2004 clearly stated, among other things, that all PNRI radiation facilities andlaboratories must be authorized by the NRD at the end of 2006. A system of authorization is
now in place for all of these facilities.
The DOH is responsible for the administration and funding of about seventy two (72) DOH
hospitals. The CDRRHR provides radiation protection services in addition to regulating
ionizing and non-ionizing radiation devices and technology.
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 two (2) Secondary Standard Dosimetry Laboratories (SSDLs) which
are being operated by the PNRI and the CDRRHR, respectively. Both SSDLs are under a
National SSDL Organization, a member of the IAEA-WHO SSDL Network, The PNRI
operates and maintains a SSDL for national standard radiation dosimetry. It continues toprovide a national monitoring service for external exposure to radiation to about 10,000 workers
occupationally exposed to ionization radiation using film badges, OSL and TLD. Internalmonitoring is not routinely conducted but in cases of probable exposure, monitoring can bedone by whole body counting or bioassay technique.
1.2.2 Number of Radiation Facilities including Related Facilities
The PNRI owns and operates few radiation facilities as follows: A 3 MW TRIGA converted research reactor (PRR-1), which became critical in 1963. The
PRR-1 became the principal facility for many research and manpower activities in thefield of radioisotope production, neutron spectrometry, neutron activation analysis, andreactor physics. By the early 1970’s routine production of some 30 radioisotopes andlabeled compounds was undertaken. The PRR-1 was converted into a TRIGA Facility
designed for 3 MW operation in 1984 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 a leak. Eventually, the PNRIManagement decided to decommission PRR-1 and have accepted to host the IAEA
Research Reactor Decommissioning Demonstration Project (R2D2P).
 Multipurpose Irradiation Facility (MIF) and the Gammacell-220 irradiator. The PNRI
provides gamma irradiation services to clients from industry, the academe and research
institutions. The MIF was upgraded in 2011 that includes addition of 150,000 curies of
Co-60 source from MDS Nordion of Canada.
 Technetium-99m Medical Radioisotope Facility. The PNRI Tc-99m facility was
installed by the Isotope Technologies, Dresden, Germany. The facility consists mainlyof 2 hot cells intended for the loading of the generators and dispensing of the Mo-99
solution to the alumina column Tc-99m generators.
Authorized practices and uses of ionizing radiation in the Philippines include the following.

 Medical uses include: a gamma knife facility; a medical cyclotron/PET facility; two (2)PET/CT facility, twenty six (26) LINACs, seven (7) Cobalt-60 teletherapy units, twenty

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FNCA Consolidated Report on Radiation Safety (The Philippines)(20) HDR brachytherapy facilities, two (2) blood irradiators and forty-one (41) nuclear
medicine facilities with SPECT capabilities; and around five thousand six hundred forty(5,640) registered diagnostic 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 of Agriculture; two hundred twenty one (221) industrial x-ray facilities andninety four (94) anti-crime X-ray facilities; one hundred thirty one (131) industrial
radiographic exposure devices; and about seven hundred (700) sources used in industrial
gauging applications.
1.2.3 Activity and Number of Radiation Sources and Generators
Table 1 gives the typical uses of radioisotopes in the Philippines while table 2 displays thecategory of PNRI licensees based on types of use or application. The PNRI adopted through an
Administrative Order the IAEA recommendation on categorization of radioactive sources and hasclassified the sources in its national registry according to this categorization system. Special
attention was given to Category 1 and 2 sources as a first priority in terms of risk based inspection
program for purposes of determining compliance with regulatory requirements.
To automate and enhance the licensing, inspection and enforcement processes, PNRI has adopted
the Regulatory Authority Information System (RAIS) developed by the IAEA. PNRI installed andimplemented RAIS 3.1 Web in 2010 and is presently in the process of migrating to the new version
RAIS 3.2 Web. Through the Management Information System Section, in coordination with the
Nuclear Regulatory Division, PNRI is currently configuring the new system and working on the
migration of existing data. Rollout and routine use of the new system is expected by the end of 2013.
The implementation of RAIS is expected to help PNRI achieve a more efficient national regulatory
control program in the country.
Table 1: Typical Uses of Radioisotopes in the Philippines

USES

RADIOISOTOPES

Hospitals

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 (Fixed
portable gauges)

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

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

Disused radioactive sources are generated from the medical and industrial application ofradioactive materials. While the licensees have the option to return disused sources to the
manufacturers, a considerable number of these disused sources are monitored and stored at
PNRI interim radioactive waste facility. Table 2 and 3 presents these inventory by source
category and radionuclide content, respectively.

Table 2: Inventory of Disused Sources by Source Category in the Philippines

Source Category

No. Of Units

1

3

2

25

3

12

4

232

5

909

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Table 3: Inventory of Disused Sources by Radionuclide content in the Philippines

Radio-

Units

Radio-

nuclidesUnits

nuclidesAm-241

78

Kr-85

33

Cd-109

8

Ni-63

10

Cf-2528

Pm-147

22

Co-57

20

Po-210

10

Co-60

149

Pu-23811

Cs-137208

Ra-226

121

Fe-55

23

Sr-90

377

Ge-68

12

Tl-2048H-3

15

others7

Ir-19261

1.2.3 Future Plans and Issues to be Resolved
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 include topics on radiation protection standards, dosimetry, personnel
monitoring, radiation control practices, emergency planning, and 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 and facilities. Several initiatives like for instance, theimplementation of a Nuclear Safety Caravan was undertaken to promote the open exchange ofsafety and security information among the various stakeholders involved in the peacefulapplication of the atom. Effective communication and exchange of information are important
tools to achieve a sustainable high level of safety and security awareness for nuclear andradiation facilities and related nuclear infrastructure in the country. The PNRI strives for the
public's proper understanding of nuclear technology and the establishment of safety culture.
This is normally achieved by providing opportunities for information exchange and addressing
the public's concerns as well as by using the collected efforts of all those involved to resolve any
public issue concerning nuclear science and technology.

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1.3 Education and Training
1.3.1 Radioisotope usage
The PNRI provides different technical services to other government agencies, privatecompanies, medical institutions, the academe, and the general public. One of these services isthe 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 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 research and the environment. Some of these courses have been
accredited by the Commission on Higher Education (CHED) with masteral units.
These training courses are offered every year to different groups such as medical
practitioners, science educators, researchers, engineers, and technicians. The courses consistof lectures, experiments, film showings, demonstrations, workshops and casestudies. Examinations are given to assess the participants' understanding of the subject matterbeing taught. Certificates of satisfactory completion are issued to participants who havedemonstrated satisfactory knowledge of the subject matter presented and the ability to apply it.
Laboratories and facilities of the different research units in PNRI are made available to thetrainees. 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 and/or application forms should be submitted together with thefollowing: Transcript of academic records
 Medical certification by nominee's Medical Officer as to his/her physical fitness toundergo training.
 Workshops /Seminars
Local workshops and seminars include specialized subjects such as the safe transportof radioactive materials and emergency planning and preparedness Thesis Advisorship ProgramThis
is open to any deserving and qualified graduate orundergraduate 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
The PNRI formally accepts on-the-job training and apprenticeship forcollege/university students and workers from other agencies who would like to learn
nuclear techniques.

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1.3.2 Radiological Protection
Education and training in radiation safety and radiological protection is provided mainly by
the PNRI. As mentioned above, the PNRI training basically aims to familiarize participants
with the fundamentals of nuclear science and technology, the basic principles of radiation
protection, and the applications of nuclear technologies in all peaceful applications. Private
societies like the Philippines Association for Radiation Protection (PARP), the Radioisotope of
the Philippines (RSP) and the Philippine Organization for Medical Physicist (POMP) also
provide specialized courses in radiation protection and technology as part of their programs andactivities.
1.3.3 Standardization on Radiation and Radioactivity
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. Metrologicalcontrols and certification of measuring equipment for ionizing radiation are conducted at the
PNRI’s SSDL to ensure compliance of radiation protection and dosimetry practices withinternational 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 of PNRI maintains the SSDL with its equipment andsource standards for the provision of services for the calibration of radiation monitoring
instruments and dosimeters (i.e. survey meters, pen dosimeter, contamination meter, personalmonitors; output calibration of brachytherapy, teletherapy and activity meters in hospitals; andradiation monitoring and hazards evaluation of radiation facilities).
Efforts to strengthen the capability for providing dosimetry and calibration services arebeing exerted to have a wider range and more practice-specific technical service. This will
ensure the accuracy 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 inthe low, 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.

Part 2. Status of Radiation Safety Management
2.1 Radiation Safety Management System
As mentioned in Part I of this report, the PNRI and the CDRRHR are the main agencies
responsible for the management of radiation safety in the Philippines. The PNRI manages thesafe utilization of radioactive and nuclear materials while the CDRRHR takes charge of allelectrically generating radiation devices including non-ionizing radiation matters.
Table 4 presents the various regulations currently issued by the PNRI. These regulations are141

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practiced specific and covers all applications in the fields of medicine, industries, research andeducation. The Institute continues 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 Code of Federal Regulations (CFR) of the United States
Nuclear Regulatory Commission (USNRC), especially those referring to the licensing of thenuclear power plant.
Table 4: Code of PNRI Regulations

CPR Part 0
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 22
CPR Part 23
CPR Part 25
CPR Part 26
CPR Part 27

PNRI as Regulatory Authority For Radioactive Materials
in the Philippines
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
Fees and Charges for Radioactive Material Licenses and Other Related
Regulatory Services, Rev.1
Licensing Requirements for Land Disposal of Radioactive Waste
Licenses for Commercial Providers of Nuclear Technical Services

Security of Radioactive Sources
Security Requirements in the Transport of Radioactive Material

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Currently, a number of these CPRs are being reviewed to ensure consistency with the current
IAEA International Basic Safety Standards (IBSS) and the Code of Conduct for the Safety andSecurity of Radioactive Sources including the additional guidance for the export and import ofradioactive sources. Appropriate security requirements in addition to safety requirements areincluded for purposes of granting authorization for the various usages of radioactive. Priority isgiven to practices using Category 1, 2 and 3 sources. Categorization of sources is practically
based on the IAEA recommendation “Categorization of Radiation Sources” which was publishedin 2000 and revised in 2003. In the interim period, these security requirements are imposed asadditional specific conditions of licenses subject to inspection and audit for compliancemonitoring.
Regulatory guidance documents, information notices and regulatory bulletins are issued topromote a common understanding of the regulations and to facilitate regulatory inspections andaudits for compliance monitoring purposes.
2.2 Radiological Protection for Radiation Workers
PNRI regulations clearly define exposure limits involving sources of ionizing radiation toboth radiation workers and members of the public. These limits strictly adhere to the IBSS
recommendations. The regulations also prescribe the appropriate corrective measures to be
implemented to control the release of radioactive materials into the environment and mitigate its
effects.
The licensees are also required to comply with the administrative and technical requirements
which include functions, responsibilities, and qualification and training of the authorized
personnel.
The PNRI ensures that the following dose limits will not be exceeded by an occupational
worker.
a) An effective dose of 20 mSv per year averaged over five consecutive years;b) An effective dose of 50 mSv in any single year; andc) An equivalent dose to the extremities (hands and feet) or the skin of 500 mSv in a year.
2.3 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 and verifies that the work areas are free from contamination.
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:a) Leak testing of sealed radiation sources;b) Radiation hazards evaluation of radiation facilities; andc) Collection, treatment, and management of disused radioactive sources, solid, and liquidradioactive wastes.
These services, provided by the Radiation Protection Section of the PNRI entail
corresponding fees. The schedule of fees for the different services of PNRI has been publishedand codified as CPR Part 22 for ease of reference of the stakeholders.
2.4 Radiological Protection for the Public
Public and environmental safety is implicitly stated as a matter of government policy for all

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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 publicfollows the recommendations stated in the IBSS. Each licensee shall ensure that the estimatedaverage 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 thatthe 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; andd) 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 with one of our meteorological station within Metro Manila is
now part of the 321 global network of the International Monitoring System (IMS) that collectdata 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.
 Access to Clean Drinking Water
 Control of Harmful Algal Bloom
 Air Pollution Characterization
 Radiological Impact of TENORM
 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.
2.5 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 PNRI NRD. The level of preparedness is commensurate to
the level of hazards expected in the facility.
2.5.1 The National Radiological Emergency Preparedness and Response Plan
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

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materials or equipment containing radioactive materials; and- 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 fromlost, 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 anactual, potential, or perceived threat to any area within the territorial limits of thePhilippines. The source may be an accident from a foreign nuclear power reactor (forexample, Chernobyl, Fukushima Daiichi), radioactive waste repositories, fuelreprocessing plants, or from the testing of nuclear weapons. This includes the possible
entry of contaminated food, plants and other commodities from affected areas outside thecountry.
d) 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.
f) Emergencies from Nuclear Ships.
This type of emergency is one that involves radioactive material or wastes from
nuclear powered sea craft including nuclear submarines.
The level of the government response to a specific emergency will depend on the type
and the amount of radioactive material involved the location of the emergency, thepotential for impact on the public and the size of the affected area. For 恵美
The RADPLAN is now undergoing review and revision to integrate security of radioactive
sources and lessons learned from the Fukushima Daiichi nuclear reactor accidents.
2.6 Radiation Safety Management in Research Reactors
2.6.1 Radiation Safety Management System
The PNRI have decided to decommission the only research reactor in the country. This
reactor called the Philippine Research Reactor (PRR-1) is one of the research reactors
considered as a test case under 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 spent enriched uranium fuel of US origin. The only irradiated fuelelements that remained were those from the TRIGA core.
There are about 115 slightly irradiated TRIGA fuel rods, plus 15 fresh TRIGA and 2 MTR
type fuel rods remaining at PNRI. The slightly irradiated fuel rods are stored in a wet stainlesssteel storage tank with 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 research reactor building.
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. All the fuel rods will be kept in storage

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until a more definite plan is made for its use.
The regulatory process for the decommissioning of PRR-1 and related activities is definedby 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 andSecurity Board was instituted to coordinate the request for authorization on the operator sideand serve as the link between the NRD and the radiation facility operators. Nuclear safety andradiological 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 CPRs.
With respect to local regulations, the decommissioning effort is committed to comply withthe following: 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.
In addition, the decommissioning of the PRR-1 will also comply with appropriate IAEA
safety standards. The project receives technical assistance from the IAEA, and the IAEA
requires such compliance as a condition for assistance. This requirement has been published in
IAEA Information Circular 127, The Revised Guiding Principles and General Operating Rules
to Govern the Provision of Technical Assistance by the Agency, March 1979.
The IAEA Safety Requirements that will notably be applied (among others) to PRR-1
Decommissioning are:
 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.
 Safety Standards Series No. WS-R-2, Predisposal Management of Radioactive
Waste, Including Decommissioning. July 2000. STI/PUB/1089.
 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 also notably
being used (among many others) to guide compliance with the IAEA Safety Requirements:
 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
and Research 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.

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FNCA Consolidated Report on Radiation Safety (The Philippines) Technical Reports Series No. 389, Radiological Characterization of Shut Down
Nuclear Reactors for Decommissioning Purposes. October 1998.
STI/DOC/010/389.
2.7 Radiation Safety in Radioactive Waste Management
2.7.1 Radiation Safety Management System
Radioactive wastes in the Philippines are generated from the various applications ofradioactive materials in medicine, industries, and research. All licensed facilities are expected
to manage the waste generated from their application in accordance with the radioactive waste
management provisions in practice specific CPRs. For short lived radioactive wastes,
The Philippines has only one (1) operating centralized facility for radioactive waste
treatment, conditioning and interim storage for all radioactive waste generated throughout thecountry. This facility is owned and operated by the PNRI inside its compound in Quezon City.
The facility has a total land area of about 4,000 m2 and a floor area of about 600 m2. The
facility includes the following: wet laboratory for R&D activities, shielded cell anddecontamination rooms, compressive strength testing area for concrete specimens, decaystorage room, chemical precipitation area, cementation area for conditioning process andcompaction area for compactible wastes. The storage room for decay has a volume of about
100 m3. 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 interim storage has an opening on one end with access from the Radioactive Waste
Management Facility (RWMF) building. The facility has a truck entrance leading to thebasement 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. An additional roofed trench is underway to accommodate incoming wastes
particularly those generated from the PRR-1 decommissioning project. These conditioned
sources are now safely stored at the PNRI interim storage facilities awaiting final disposal.
The PNRI continues to pursue the upgrading of its centralized facility for low to intermediatelevel radioactive waste treatment facility with assistance from the United States Department ofEnergy (USDOE) relative to the improvement of the physical protection and security aspects.
The PNRI adopts two (2) basic waste treatment and conditioning options for radioactive
waste. These are (a) waste collection and packaging for decay storage for final disposal as
ordinary refuse; (b) waste collection, segregation, treatment, conditioning and packaging,followed by interim 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 inaccordance with a system established for the purpose.
Authorization to operate, treat, and condition radioactive waste has been granted for thewaste store facility by the NRD of PNRI pursuant to PNRI Policy Instruction No. 02 Series of2001, “Radiological Health and Safety Policy” and PNRI Office Order No. 002 Series of 2004
“Regulatory Control Program for PNRI Nuclear and Radiation Facilities and Laboratories”.
Regular inspections are also carried out to verify regulatory compliance.
Two important regulations govern the safe management practices of radioactive waste in the147

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Philippines. These are:1) The Code of PNRI Regulations (CPR) PART 3 entitled Standards for Protection Against
Radiation provides for the general requirements involving waste management anddisposal of licensed radioactive material include (a) storage under controlled conditions,(b) control and monitoring of environmental discharges, (c) regulatory limit for airborne
and waterborne discharges adopting the IAEA Clearance Levels for waste resulting frommedical, 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 waste materials. In the case of disused sources, the licensee has thefollowing options in the management of disused sealed sources: (a) return to theprincipal, original manufacturer or supplier, (b) transfer of source to another licensee forapplication or use at the current activity level, (c) decay storage of short half life disused
sources. These options should be thoroughly considered prior to disposal at the PNRI
Centralized Radwaste Treatment and Storage 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.
2.7.2 Criteria to define Waste Category
The present regulations do not specifically define the criteria for waste category. However,guidance from the IAEA is being used whenever practical to ensure safety and regulation.
2.7.3 Managing sources at the end of their life cycles
All authorized users of radioactive sources have the following options in the management of
disused sealed sources: (a) transfer of source to another licensee for application or use at thecurrent activity level, (b) decay storage of short half life disused sources, (c) return to theoriginal manufacturer or supplier. These options should be thoroughly considered prior to
final management at the PNRI Centralized Radwaste Treatment and Storage Facility.
In March 2013, the IAEA through a contract with NECSA and funded under the Nuclear
Security Program managed to transport and assemble its mobile hot cell unit inside the PNRI
compound to condition Specific High Activity Radioactive Sources (SHARS) currently instorage. Over a six-week period, NECSA successfully conditioned 13 units of teletherapy
sources and 3 irradiator sources. The conditioned sources are now safely stored in two (2) longterm storage containers awaiting final disposal. All other disused sources returned to PNRI for
management are conditioned in 200 liter concrete lined drums and placed at the interim storage.
The PNRI in collaboration with the interagency technical committee on radioactive waste
has been undertaking a national project to find a final and sustainable solution to the country’s
low to short lived intermediate level radioactive waste. The strategy adopted was to co-locate
2 disposal concepts that will address the types of radioactive waste generated from the use ofradioactive materials. Given the small volumes of waste expected as compared to a country
with an advance nuclear program, the strategy adopted is deemed commensurate and feasible

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for the country to pursue. It will also take advantage of the benefits of a shared infrastructure
and R&D works that accompany such project.
A preferred site located in the northern part of the country was selected and is currently the
subject of detailed investigation. The footprint of the site has about 40 hectares for potential
development. The geology of the site is characterized by andesitic pyroclastic
All activities take into consideration not only the requirements set out in the appropriate
PNRI regulations mentioned above but also international best practices practicable in theselection, design and operation of the envisioned co-located radioactive waste repositories.

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10. Thailand
Part 1. Radiation Safety in Radioisotope Facilities .......................................................................... 151
1.1 General ............................................................................................................... 151
1.1.1 Legislation and regulations .............................................................................................. 151
1.1.2 Structure and System (Regulatory organizations) ........................................................... 152
1.2 Outline of Radiation Facilities and Radiation sources ................................... 153
1.3 Education and Training .................................................................................... 155
Part 2.Status of Radiation Safety Management ................................................................................ 156
2.1 Radiation Safety in various RI usage .............................................................. 156
2.1.1 Inspection Program .......................................................................................................... 156
2.1.2 Dose Limit of Radiation Workers .................................................................................... 157
2.1.3 Radiological Protection for the RI User .......................................................................... 158
2.1.4 Radiological Protection for the Public............................................................................. 158
2.1.5 Radiation Emergency Preparedness ................................................................................ 159
2.2 Radiation Safety Management in Thai Research Reactor-1/ Modification1 (TRR-1/M1) ............................................................................. 162
2.3 Radiation Safety in Radioactive Waste Management .................................... 164
2.3.1 Related law and regulation on Radiation Safety and Radioactive Waste Management . 165
2.3.2 Safety assessment of Thailand Radioactive Waste Management Facility. ..................... 166
2.3.3 Assessment Endpoints...................................................................................................... 169
2.3.4 Safety Management of Disused Sealed Source............................................................... 169
2.3.5 Radiological Protection for Radiation Workers............................................................... 169

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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 anddevelopment of nuclear technology and towards a better standard of living. Since 1961, the
OAEP has had the roles of promoting nuclear technology, providing services, as well as
regulating.
Recently, the R&D tasks on nuclear applications and related nuclear service activities has
been separated from the OAEP. The nuclear application and R&D activities are carried out by
the Thailand Institute of Nuclear Technology (TINT), as an implementer of nuclear research
activities and nuclear technology services. In addition, the OAEP was renamed to be the“Officeof Atoms for Peace “(OAP), plays as the regulatory body arm to control the use of radiation andnuclear applications in Thailand by the authorization from the Thai Atomic Energy Commission(Thai AEC).
At present, there are about 20,000 licenses including X-ray and radioactive source possessions
and utilizations in the country. These licensees are a heterogeneous mixture of individual andgovernmental institutions which possess the radionuclide of activity ranging from a few kBq up tosome more than GBq. The type of nuclear facilities, radiation generation facilities and radionuclide
utilizing facilities are vary on the development of the atomic energy techniques and applications. At
present, Thailand has no nuclear power plant (NPP), but the feasibility study on NPPand some
NPP preparation activities was conducted by the Ministry of Energy and the Electricity
Generation Authority of Thailand (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 and also
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 radioactive151

FNCA Consolidated Report on Radiation Safety (Thailand)waste before transport to the centralized RWM in the country ( it was the OAP in thattime). 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, clearance
level of solid, liquid, and gaseous waste. However, this regulation need to be revised forthe up to date conditions in the present time as well as for the harmonization with thedevelopment of international standard in several issues. Up to now, there is no specificregulation for RWM facilities, such as the licensing system of RWM facilities.
1.1.2 Structure and System (Regulatory organizations)Regarding to the Atomic Energy for Peace Act (1961), the Thai AEC plays role of National
Regulatory Body. The OAP, Ministry of Science Technology (MOST) plays as a regulatory
functional arm of Thai AEC. The OAP Secretary General is as the secretariat of the Thai AEC.
There are several sub-committees appointed from external experts and OAP staff to review all
matters related to the regulatory function. The OAP has been authorized by the Thai AEC toregulate, control as well as pre-review the license of the production, possession, and utilizationof 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 promoting activities and some services are still done by OAP.
However, some issues 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 needs to be revised and improved.
Thai Atomic Energy Commission
Ministry of Science and Technology(MOST)

Office of Atoms for Peace(OAP)
Bureau of Radiation Safety Regulation
Bureau of Nuclear Safety Regulation

16 Sub-committeesMedical Application



Agricultural Application

Industrial Application

Licensing of Radioisotopes
and Nuclear Materials

Nuclear Safety
and etc.

Bureau of RegulationSupporting
Non-regulatory groups
Figure 1: Nuclear Regulatory Organizations in Thailand

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1.2 Outline of Radiation Facilities and Radiation sources
Table 1: Type of Radiation and Nuclear 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 ( Gems-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 k Bq up to some GBq are possessed in many
areas of applications. There are several radionuclides produced in the country byRadio-Isotope Production Center,TINT, such as I-131, P-32 and Sm-153.
Several radionuclides are used in R&D, medicine, and industry, such as Am-241, C-14,
H-3, I-125, I-131, Sm-153, Cs-134, Cs-137, Co-60, Sr-90, Kr-85, and etc.
 Accelerators
There are several accelerators in uses for educational and R&D institutes, such assynchrotron, neutron generator, and electron beam.For the hospitals and clinic, linear

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accelerators (LINAC) and PET cyclotron are usedfor radio-therapy.
 Distribution of radioisotopes
Table2: Distribution of radionuclide use by its applications.
Category
application

byRadionuclide

Percent (%)

Remarks

MedicalGa-67,Cr-51,Tc-99m,
Co-60,I-125,
I-131,Tl-201,
H-3,C-14,P-32,
S-35,Ra-226,
Sm-153,Sr-90 and etc

13

SRS and RI

Education
and Research

P-32,S-35,Cr-51,Ca-45,
Tc-99m,I-131,Co-60,
Sr-90,Cs-137,
Am-241, Be and etc.

30

SRS and RI

Industrial

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

40

Most are 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
129
Industry
377
Research & Education
280
Others (smoke detector, lightning preventer)160
Radiation User Licensee
Medical X-ray devices

8500

Industrial and Security X-ray devices

1500

Medical Electron accelerators (LINAC)

35

Custom Electron accelerators

10

PET cyclotron(medical)

3

Synchrotron (R&D)

1

Neutron Generator (education)

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 preparednessand etc, as follows:









Training Course on Radiation Protection for General Radiation Workers (Level 1).
Training Course on Radiation Protection for General Radiation Workers (Level 2).
Training Course on Radiation Protection for Radiation Supervisors (Level 3).
Training Course on Emergency Preparedness for General Workers.
Training Course on Radioactive Waste Management for Radioactive Material Users.
Training Course on Radiation Safety Officer (RSO)
Training Course on Emergency Preparedness for TINT Emergency Team staff.
Refreshment Course on Radiation Protection for TINT staff (every 2 years)
and etc.

TINT- In House Radiation Protection Training
The radiation protection training is conducted by the Academic Service Unit, TINT, which
cooperated with the Safety Unit. It is structured at different levels in order to meet the needs ofstaff 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 by an 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 overthe following outlined topics in sufficient depth for the work being done and pass a written
examination with a minimum grade of 70%.

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FNCA Consolidated Report on Radiation Safety (Thailand)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.

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 theAtomic Energy for Peace Act B.E.2504 and Ministerial Regulation B.E. 2550. The main issues
are comprised 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 nuclear materials and radioactive materials
2.1.1 Inspection Program
The OAP has established a planned program for inspections of radioactive sources. The
frequency and extent of inspection depend on: 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 with156

FNCA Consolidated Report on Radiation Safety (Thailand)

the categorization number
Table 4: Radioactive Source Categorization System (OAP, 2007).

Category

Source and practice1

Radioisotope 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

2

3

4

5

Duration ofLicense/Inspection

1year/annually

2years/ every 2 years

3years/ every 2 years

4years/ every 2 years

5years/ every 2 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,
Ministry of Health which has the accreditation following ISO-17025.
The Department of Medical Science is to providedosimetry laboratory services forradiation workers in the country through its Secondary Standards Dosimetry Laboratory(SSDL) since 1971. The Department of Medical Science’s dosimetry laboratory is a memberof the International Atomic Energy Agency and World Health Organization. It has an excellent
cooperation network in South-East Asia.
The OAP-dosimetry laboratory carries 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 thecalibration of radiation monitoring instruments and dosimeters (i.e. survey meters,rate meter,
personal monitors, etc.).
2.1.3.2 Radiation Safety Service
The users can also request technical services from the TINT to ensure safety in theirfacilities.
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 ofservice-charge for the different services of TINT has been published as a reference for the
stakeholders convenience.
2.1.4 Radiological Protection for the Public
Dose limits to the public follows the recommendations stated in the OAP- regulation basedon 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 :
1. In addition, the TINT provides services, upon requests, on the certification of radioactivity
content of food stuffs for export.
2. The OAP has provided services on Internal Dose checking during the Fukushima Daiichi
Nuclear Power Plant Accident in 2011, as shown in Fig.2

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FNCA Consolidated Report on Radiation Safety (Thailand)Internal radiation dose check at the OAP• I-131 dose check for several public groups– General public– Private company employees– Government officials such as air force personnel• No contamination found10
Figure 2: Service on Internal Radiation Dose Checking at the OAP

2.1.5 Radiation Emergency Preparedness
Emergency Planning and Preparedness is a 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
to the level of hazards expected in the facility.


National Nuclear and Radiological Emergency Plan

As a specific regulation in the emergencypreparedness and response field, the “Act ofDisaster Prevention and Mitigation” has been promulgated in 2007.
At the top level there is a national emergency plan for an integrated response to any
combination ofhazards. The National Preparedness Plan which includes the National Nuclear
and Radiological Plan (NNREP) is part of this “allhazards” plan.
The Bureau of Radiation Safety Regulation, Office of Atoms for Peace (OAP) acts as a
National Competent Authority and Technical Support which coordinate to both regulatory
bodies and response organizations. The Department of Disaster Prevention and Mitigation(DDPM) is the principle government agency for the National Disaster Prevention and
Mitigation acts as 1st Responder and/or Decision maker. The structure of the national
preparedness plan and the photos of emergency preparedness and response exercises are shownin Fig.3 and Fig.4 respectively

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FNCA Consolidated Report on Radiation Safety (Thailand)•Structure of the National Preparedness Plan

Licensees’
Plan

Figure 3: Structure of the National Preparedness Plan

Figure 4: Emergency Preparedness and Response Exercises under the National Preparedness Plan

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Radiation Monitoring Program around the country
There are 12 monitoring stations throughout country including 2 stations in the sea at the
Gulf of Thailand and the Andaman sea, and the real time radiation level is available at the OAP
as shown in Fig.5.

Real‐time Radiation Level Update
on OAP website

19
Figure 5: Real-Time Radiation Monitoring around the Country.

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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
so that two major types of radiation surveys are carried out; referring as routine radiation level
and contamination 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 exit.
Radiation workers must also wear at least one type of personal dosimeters. TLD’s are issued toeach radiation worker every 3 months. Digital dosimeters-direct reading personal dosimeters areprovided for both radiation workers and visitors. Visitors must be escorted by an Operator. The
number of visitors in a single occasion must not be greater than 20 persons.

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The ALARA program is based on the guidelines found in Basic Safety Standards for
Radiation 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 radiation and 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

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entering the TRR-1/M1 receive training in radiation protection appropriate for their work/visit, orshall 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.
The 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.
 Radioactive Waste Management Operation
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(Table 5.) Currently, there is no disposal facility in Thailand. The RWM process is shown in Fig.
6.

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Fig.6 Radioactive Waste Management Process in Thailand Regulatory Framework
The nuclear regulatory function is conducted by the OAP. The RWM regulation andguidance was first implemented in 2003, under the Atomic Energy for Peace Act B.E.2504(1961) and the Ministerial Regulation on Rules and Procedures of Radioactive Waste
Management B.E.2546 (2003). Up to now, there are no specific regulations on licenses forradioactive 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

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FNCA Consolidated Report on Radiation Safety (Thailand) OAEP-20 Guides of RW Segregation, Collection, Container and Label OAEP-21 Guides of Temporary Storage for RW Generator

Table 5: Radioactive waste management facilities in Thailand
Facilities
Solid waste treatment

Items
Incinerator equipped with off gas
cleaning system
Compactor
Chemical precipitation plant

Capacity
15 kg/hr

Type of Waste
Burnable waste

40 ton5 m3/batch

Conditioning

Stainless steel container
In drum cement mixer

2 x 5 m3
200 Liter

Compactable waste
Aqueous waste with low
salt content
Organic liquid waste
Ash, sludge

Storage

Storage facility No.1

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

Liquid waste
treatment

Storage facility No.2

Note: the newstorage will be
operated soon

Storage facility No.3
(at Pathumthani Province)

300 m2 x 5 m

Storage facility No.4 (at Ongkarak
site, NakhonNayok Province)

1050 m2x 6 m

Disused SRS
Treated Waste indrums;ashes, sludge
Treated Waste in drums:
DSRS

Treated Waste in drums:
DSRS

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 forpredisposal waste management facilities or activities is provided in IAEA Safety Guides DS284.
The recommended approach to safety assessment is outlined in Fig 7 and 8. It includes thefollowing 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;

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FNCA Consolidated Report on Radiation Safety (Thailand)(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 outlinedin Figure 2 are interdependent and should be performed in an iterative manner. Solidblack lines indicate the typical sequence of activities but this sequence is notmandatory. Dotted lines indicate possible changes to this sequence, for example if ahazard is screened out there is no need for further modelling. Similarly the“Assessment Context” may change as a result of subsequent stages in the safetyassessment process.

Figure 7: TINT Waste Stream Diagram.

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Purpose,Regulations, Standards …

Assessment Context

Engineering Design
Safety Measures
Other relevant information(Management systems, operational

Description of Facility or Activity
and Waste

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

Independent
verification

Case?

Adequate?

ReviewandmodifyFigure 8: 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 thandose are 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 occurred in Thailand in the year of 2000.
Consequently ,the 400 Ci disused Co-60 teletherapy sources became open. The Co-60 source
was dropped down in a scrap metal shop. The OAP emergency team successfully recovered thesource and then the subsequent management, conditioning operation of the source have beensuccessfully completed in 2001.
During the year 2000-2002, all the disused Radium-226 around the country collected by
the Thailand team with the cooperation of an IAEA expert. All the collected Radium-226
were successfully conditioned in the year of 2004. In addition, the conditioning operation of 4
Ci Ra-226 external source was also successfully conditioned by OAP team (TINT at present) inthe year of 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, the TINT-RWMC in collaboration with other government agencies, such as
MEXT/JAEA, FNCA, KAERI, and US-DOE is working for the safety management ofradioactive 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.
 Summary of Radiation Safety in Radioactive Waste Management• Radioactive Waste Management Center, TINT acts as the centralized Radioactive Waste
Management Facility in Thailand• The Radioactive Waste Management Center is in charge of waste management operation suchas collection, transportation, segregation, treatment, conditioning, and storage• Low level solid wastes are treated by incineration and compaction

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FNCA Consolidated Report on Radiation Safety (Thailand)• Low level aqueous wastes are treated by chemical flocculation-precipitation, andion-exchange method.
• The treated wastes are solidified by cementation in 200 liter-drums.
• Treated Wastes in Drums are kept in the TINT storage facilities.
• New Radioactive Waste Storage facility is located at the new site, Ongkharak District and will
be operated around the mid of 2014.

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11. Vietnam
Part 1. Radiation Safety in Radiation Industry Facilities ................................................................. 172
1.1 General ................................................................................................................................ 172
1.1.1 Legislative framework and policy for radiation safety ................................................... 172
1.1.2 Regulatory Body .............................................................................................................. 172
1.2 Outline of Radiation Facilities and Radiation Sources ...................................................... 173
1.2.1 Number of specialists and workers in related organizations ........................................... 173
1.2.2 Uses of radiation and nuclear in Vietnam ........................................................................ 173
1.3 Education and Training ....................................................................................................... 178
1.4 Standardization on Radiation and Radioactivity ................................................................ 179
Part2. Status of Radiation Safety Management ................................................................................ 180
2.1 Radiation Safety Management System............................................................................... 180
2.2 Radiation Safety Management............................................................................................ 181
2.2.1 Radiological Protection for Radiation Workers............................................................... 181
2.2.2 Radiological Protection for Radiation Area..................................................................... 182
2.2.3 Radiological Protection for the Public............................................................................. 182
2.3 Emergency Plan for Radiation Accident ............................................................................ 183
2.3.1 Plans for radiation incident response ............................................................................... 183
2.3.2 Responsibilities of related organizations individuals in case of incidents ...................... 184
2.3.3 Training and Practical Exercises ...................................................................................... 184
2.4 Radiation Safety Management in Radioactive Waste Management .................................. 184
2.4.1 Radioactive Waste Management...................................................................................... 184
2.4.2 Site selection for Low Level Radwaste Central Facility ................................................. 186

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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.
In November 2011, Vietnam and Russia signed an inter-government agreement on theconstruction of the nuclear science and technology center to help develop Vietnam’s nuclear
power program. with the investment capital of $500 million. The capital would be loaned by the
Russian government at preferential interest rate.
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.
1.1.2 Regulatory Body:
MOST: Under the Article 29 of Ordinance and the Article 34 of Decree 50/CP the MOST
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.
VINATOM: Under direction of the MOST, the VINATOM is responsible for conducting all
R&D activities in the field of the application of nuclear energy in Vietnam and assisting the
VARANS on technical aspects.

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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.
VAEA: Vietnam Atomic Energy Agency under MOST, which advise and assist the Ministerto fullill the State management functions for research, use and develope nuclear energy
nationwide carry out professtional activities in the Agency’s management function.
DOST: The 63 Provincial Departments of Science & Technology (DOSTs) are responsible
for radiation protection and nuclear safety within the province under supervision by VARANS.

Figure 1: Structure and resources of regulatory body and supporting organizations

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 relatedorganisations. 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
Accoring to inventory data from VARANS in July 2013, in Vietnam , there are 803
radiation facilities and 2,930 X-ray diagnose facilities. There are 1413 radioactive sources instorage and 1797 radioactive sources in use in difference areas, including:-Industry: 1121
Health care: 91
Education & Research: 293
Others: 292

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FNCA Consolidated Report on Radiation Safety (Vietnam)

Figure. 2: The percentage of radioactive source in use in different areas
The largest radiation facilities are:
 There is only one nuclear installation in the country is the Dalat nuclear research
reactor with capacity of 500 kW.
 One cyclotron 30 Mev built in 108 Military Hospital (Hanoi city) and the PET-CT& Cyclotron in Cho Ray Hospital (Ho Chi Minh city) in operatation in 2009
There are 824 radioactive facilities in operation in Vietnam by July 2013 (inventory fromVARANS) including: Industry: 441
 Health care: 65 (without X ray facilities)
 Education & Research: 49
 Radiation Safety Services: 11
 Business: 202
 Others: 56

Figure. 3: The percentage of radioactive facilities in operation in different areas

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Accoring to inventory data from VARANS in July 2013, there are 803 radiation equipments(without X ray equipments) in operation in different areas in Vietnam:
 Industry: 406
 Health Care: 169
 Education & Research : 54
 Other: 174

Figure 4: The number of radiation equipment in operation in different areas

Figure 5: The number of radioactive sources and radiation facilities in operation in Vietnam

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

Number of Facilities

Planned

In operation

Not in operation

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

1

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

1

Tele-therapy

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

3

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

33

0

4

NDT (radioactive source)

23

0

5

Gauge (fix)158

6Well logging

12

0

7

Tracer1

0

8

X-ray fluorescent analysis

59

0

9

Main-board Scanner

1

0

2

49

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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 logging

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.

Application1

Education & Research

Number of Facilities
In
Not inoperation
operation
Education & Research
27

Planned0

Others1Agricultural irradiators

0

2

2

Geology

1

3

3

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

8

0

0

0

4

1 gamma field (DaLat)

Table 6: Number of sources in education, research& others
No.

Application

Sealed Source
In UseIn Storage

X-Ray

Unsealed
SourceAccelerator

11

X

1

Education & Research
1

Education & Research

327

105
Others1Agricultural irradiators

0

2

2

Geology

4

120

0

X

0

3

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

0

0

97

0

0

0

0

0

0

0

4

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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 controlledareas.
 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 Services

No.

Type of Services

Number of Facilities

1

Providing personal Dosimeter22

Calibration of Radiation Survey meter

2

3

Radiation Monitoring (measuring the dose rate)21

4

Calibration of X-ray Machine in Health Care

17

5

Training in the radiation protection

VINATOM + VARANS +DOSTsNational 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 abasic 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.
- Ho Chi Minh City University of Science has a Department of Nuclear Physics. It wasestablished in March, 1996. Currently provides around 50 graduates annually with a basic
degree in nuclear physics for the South of Vietnam.
- Dalat University is the other university which offers courses on nuclear science and it
produces about 20 graduate students annually.
- On 26 October 2001, the Ministry of Education and Training decided to upgrade theElectrical Engineering School No. 1 to Electric Power College. On 19 May 2006, the Prime
Minister issued a decision to establish Electric Power University (EPU) formerly the ElectricPower College, operated directly under Electricity of Vietnam (EVN). EVN is the country''s
economic group operating in the field of electricity. In respond to the training needs, for the energy
sector, especially nuclear energy, EPU has developed curriculum on nuclear power.
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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 reference radioisotope sources.
In the personal dosimetry network, VINATOM and VARANS are presented as authority. In
this network, there are two recognized personal dosimetry service centers: INST (Hanoi) andNRI (Dalat), which will provide individual monitoring service for the radiation workers in thewhole country.
 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 VINATOM and VARANS, to the supervisorsof radiation workers.
Secondary Standard Dosimetry Laboratory (SSDL)
INST(Hanoi) operates and maintains a SSDL for national standard radiation dosimetry
and calibration of radiation protection instruments such as survey meter, pocket dosimeterbut it is limited in scale.
Intercomparison and international supports in increasing accuracy and personal
dosimetry management are essential. The intercomparisons were good way and very usefulfor finding the problems in our system and help us to gain confidence and improve theaccuracy of personal dose equivalent estimation.

Figure 6: The TLD Reader
HARSHAW 4500

Figure 7: Calibration Instruments

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Part 2. 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.

TCVN 1638 – 75
TCVN 4397 – 87
TCVN 4498 – 88
TCVN 4985 – 89
TCVN 5134 – 90
TCVN 6053 – 95
(ISO 9696:1992)
8. TCVN 6053 – 95
(ISO 9697:1992)
9. TCVN 6561:1999
10. TCVN 6730-1:2000
11. TCVN 6866:2001
12. TCVN 6867:2001
13. TCVN 6868:2001
14. TCVN 6869:2001
15. TCVN 6870:2001
16. TCVN 7077:2002(ISO 1757:1996)
17. TCVN 7078-1:2002(ISO 7503-1:1988)
18. TCVN 7173:2002(ISO 9271:1992)
19. TCVN 7174:2002(ISO 9271:1992)
20 TCVN6941:2013
21

TCVN6942:2013

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
Nuclear Safety – External human induced events in site
evaluation for nuclear power plant
Nuclear Safety- Survey and evaluation radioacive dispersions

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22

TCVN6943:2013

23

TCVN6944:2013

24

TCVN6945:2013

in air, water, - Consider population distribution in site
avaluation for nuclear power plant
Nuclear Safety- Geotechnical problems in foundation &site avaluation for nuclear power plant
Nuclear Safety-Survey and Evaluate the dangerous ofearthquake for nuclear power plant
Nuclear Safety-Survey and
Evaluate of meteorology,hydrology in site avaluation for nuclear power plant

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 designof processes 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 contaminantsfrom the workplace environment; 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.
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 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

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Reference: Occupational Radiation limits for radiation worker were given by TCVN 6866:2001.
About 6,300 of radiation workers in the country are monitored occupational dose. The duties and responsibilitiesof 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 mechanicalventilation 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
scheduled and also at request
2.2.3 Radiological Protection for the Public
Monitoring for radionuclides is carried out continually to determine compliance with thelimits imposed by the regulator and to fulfill the duty to protect members of the public. The
environmental radiation monitoring network have been established with goals:- Provides systematically data on ambient levels of radiation in the environment (during
routine as well as emergency conditions) - Provides data for nuclear emergency response
assessments (making decision necessary to ensure the protection of public health)- Provides data for professional studies and Informs the general public and public officials.
- Provides national database of environmental radiation for serve the State management in
the field of atomic energy and nuclear safety

Figure 8: The structure of the National NetworkConstruction & Management of the Network
Circular No 27/TT-BKHCN-MOST (30/12/2010)- VINATOM will be responsible for building and managing the National control Centerand the areal Monitoring Station. Annually, VINATOM report the environments
radiation status to MOST and report immediately when there is abnormal phenomenonof radiation.

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FNCA Consolidated Report on Radiation Safety (Vietnam)- DOST of the provices and center cities will be responsible for building and managing
Local Station on the basic of the network.
- Organization and individuals operating the nuclear facilities (NPP, research reactor,
uranium enrichment facilities, nuclear fuel fabrication, disposal facilities, storage andburial of radioactive waste and energy nuclear materials used ) will build and manage
their own monitoring station.
 Roadmap and Network Building
Period 2010-2015- Develop and put in to operation National Control Center- Consolidate the 4 areal stations and six local stations and set up a working group at thestations- Gradually increase the capacity of technical support of emergency response- Set up station at areas where we build NPPs
- Organize training and retraining staff for environmental radiation monitoring andanalysis- Complete regulations on organization and operation of network building legal documents
standards technical regulations.. for environmental radiation monitoring and analysis- Set up a National database of environmental radiation monitoring
Period 2016-2020- Build and put in to operation the station and the rest in planning- Consolidate the comprehensive and unified commissioning the entire network- Continue investing in capacity building monitoring and analysis of the network ensure
reasonable consistent uniform, mordern network monitoring & warning of advanced
countries in the region Southeast Asia
- Concentrate investment in technical capacity of the network to support emergency
response operations of nuclear power plants- Further improve the national database on environmental radiation
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 People’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.

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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 theout 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 thecause of the incident.
2. Responsibilities of the agencies, organizations, superior to the organizations, individuals
conducting radiation activities:
3. Responsibilities of Province People’s Committees:
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:
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 VINATOM 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 occurring
radionuclides (NORM) and technologically enhanced naturally occurring radioactive materials(TENORM) are produced in Vietnam by the mining, mineral sands processing and otherresources sectors. Vietnam has no nuclear power plants.
So far, Vietnam has no national used radioactive sources and radioactive waste storage
facility There are four largest RWM facilities, they belong to nuclear or radiation facilities inVietnam:
1) The system for RWM at the DNRI (Dalat Nuclear Research Institute)
DNRI is responsible for the management of radioactive waste at the national level in
Vietnam, and collects, transports, treats, conditions, and stores radioactive waste
generated from operations from radiation facilities in the South of Vietnam. In orderto carry out this mission, DNRI has employed a system for radioactive waste
management based on the former USSR regulations valid since the beginning of the
1980s. This system was renovated and modified during the years of 1995-1997 by
IAEA TC projects and national projects. After conditioning, the waste drums are stored in184

FNCA Consolidated Report on Radiation Safety (Vietnam)

building #5 (radioactive storage building).
The Institute generates a total of about 100-150 m3 of radioactive liquid waste andaround 5 m3 of dry and wet solid radioactive waste each year, mainly from reactor
operation and radioisotopes production activities.
The system for radioactive waste management at DNRI consists of 2 main buildings:• The radioactive liquid waste treatment station is located underground at minus 4 m,
and includes storage tanks, an evaporation system (currently installing), and a
distilled water system. There are also two Laboratories, and a control room on the
ground floor.
• An interim storage building (referred to as Building #5) has a compaction system, andeight concrete cells for storage of compacted solid waste and used radioactive
sources.

Figure 9: An interim storage building in Dalat Nuclear Research Institute2) The Interim Storage Facility at the Institute for Technology of Radioactive and Rare
Elements (ITRRE) at Phung, Hanoi City;
In this facility, all radioactive waste from research activities of ITRRE, mainly
from uranium, rare - earth ore processingare are collected, classified, treated and stored
in interim storage. There are 733 reinforced 200l drums.
Annually 3 month, the environmental radioactivity monitoring are carried out by
radiative officer of ITRRE to ensure the radioactive safety for worker and surrounding
areas.

Figure 10: The RWM facility at Phung, Hanoi (inside)185

FNCA Consolidated Report on Radiation Safety (Vietnam)

3) The sealed sources store at Luong son, Hoa binh, (40km from Hanoi)
It was constructed in 1983. The used sealed sources and standard sources using in
the geological and industrial areas are stored in the reinforced concrete pits

Figure 11: The sealed sources store at Luong son, Hoa binh4) The sealed sources store in Institute for Nuclear Science and Technology (INST)(Hanoi)This facility stores used radioactive sources from research activities of INST andother radioactive facilities in the North of Vietnam
5) The sealed sources store in NEAD (be long to VINATOM) – 140 Nguyen Tuan street– Hanoi.
It was constructed in 2003 and in operation in 2004. It stores about 250 used sources,from other radioactive facilities, activity total: 43.69 Ci (21/6/2010) (the data fromVARANS, July, 2013)
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 Usesof Atomic 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. Official studies on
meteorological, geological and hydrogeological conditions of Vietnam show that on the territoryof Vietnam, 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 3 most suitable candidate sites: Tu Thien village, Son Hai village, Ninh Phuoc
district and Thai An village, Ninh Hai district, Ninh Thuan Province. They are near the site forbuilding of the first nuclear power plant .

186

IV. Contributors
Australia
Mr. Lubi Dimitrovski
Australian Nuclear Science & Technology Organisation (ANSTO)
Ms. Lynn Tan
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)Ms. Takako Shiraki
Mitsubishi Heavy Industries, Ltd
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 Co., Ltd.
Mr. Toshiharu Miyakawa
Japan Nuclear Fuel Limited (JNFL)

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Dr. Yuji Matsuzoe
Fuji Electric Co., Ltd.

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

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

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

Vietnam
Dr. Le Ba Thuan
Vietnam Atomic Energy Institute (VINATOM)
Ms. PHAM Thi Quynh Luong

Vietnam Atomic Energy Institute (VINATOM)

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