Nine country papers were presented in Session II

With regard to radiation safety the Australian guidelines are based on IAEA safety documents and reflect best international practice. The Safety Guidelines include codes of practices and technical reports. The adherence to ALARA principle is a high priority in managing radiation safety in Australia.

The present Federal Government has decided to put on hold further progress in the establishment of the co-located LLW repository and ILW storage facility. The site characterization studies of 4 potential sites have been completed with all 4 sites deemed suitable.

The participants were also briefed on the decommissioning program for the HIFAR and MOATA research reactors. HIFAR was shutdown on 30 January 2007 and MOATA in 1995. The HIFAR reactor is currently under a Possession and Control License waiting final dismantling and decommissioning planned to commence in 2017. The process of decommissioning of the MOATA reactor is proceeding with completion scheduled for December 2009. All spent fuel arising from the operation of these reactors has been sent to the UK and France (for reprocessing) and the US (as part of the spent fuel take-back program for research reactors).

ANSTO has commenced producing Mo 99 from a new alkaline-based process. Low level wastes produced from Mo 99 production will be processed by existing radioactive waste management facilities. The intermediate level solid and liquid waste will require new waste processing streams. Work on the new process methodology is currently in progress.

The Nuclear Safety and Radiation Control Division, which is under the Bangladesh Atomic Energy Commission, is the regulatory authority. Legislation frameworks are in existence. Any activities related to the radioactive materials, nuclear materials and radioactive waste require a licensing process.

Currently there is no radioactive disposal facility in Bangladesh. All processed and unprocessed wastes are safely stored in a central storage facility with a defined radioactive waste inventory in place. At present Bangladesh does not have a spent fuel management system.

There is a well defined and managed NPP and research reactor spent fuel inventory in China. In terms of the legal framework there are independent regulatory systems for spent fuel and radioactive waste. Radiation safety in China is based on the IAEA basic safety standards. Currently, there are about 8.3 tons of spent fuel and 5000 m3 of radioactive waste from research reactors stored within China. Dr Fan also made not to the large construction program for new NPP 's with a total of 18 new NPP 's currently in process.

An integrated approach to reform the radiation protection system in SNA was recommended, with the application of dose constraints, uniform area classification, introduction of incident event reporting and the use portable contamination monitors in all controlled areas. Some of the recommendations were followed through by SNA (e.g. re-training of staff and uniformity of labeling) but a second IAEA review conducted in 2008 found that only 20% of the previous recommendations were implemented. The report findings re-emphasized the need to set up dose limits, monitor stack emissions, upgrade radiation protection instruments and to conduct regular auditing. SNA responded to the review with the setting up of a Central Authority as a higher authority to integrate and control the implementation of radiation protection and environmental monitoring for the site in accordance with international standards.

Japan 's adoption and implementation of the ALARA principles is evident, with total gaseous and liquid releases into the environment reducing in the face of increasing number of nuclear reactors in the country. In the area of staff radiation safety, the centralised occupational exposure dose records shows that the total collective dose has dropped from 110 mSv person in 1985 to 80 mSv person in 2007. This is the result of improvement in maintenance work and work practices within in the nuclear industry and in particular nuclear power plants. The annual volume of radioactive waste received at the low level waste repository has also decreased steadily. The various waste package types and waste disposal processes in Japan were also detailed.

Several other new regulations are also being drafted including regulations on Nuclear Installation Licensing and Radioactive Waste Management. Malaysia is planning to build their first nuclear power reactor by 2025. In line with other nuclear institutions and nuclear power industries, Malaysia is progressing in the area of radiation safety training to ensure that trained and competent workers are available to address this critical area in the nuclear industry. Details on Malaysia 's Environmental Radiation Monitoring System (ERMS) were provided with several EMRS locations already established and operational within the country. Portal monitors are also situated in various airports, seaports and borders to prevent illicit trafficking of radioactive materials. All data is transmitted 24/7 to the central control at AELB.

The 3-MW TRIGA converted research reactor serves as the model reactor for the IAEA research reactor decommissioning demonstration (R2D2) project. The Philippine government is currently exploring the possibility of rehabilitating the 620 MW PWR type Nuclear Power Plant located in Bataan. A feasibility study is currently being conducted by Korea Electric Power Company (KEPCO) and a detailed report is expected before the end of 2009.

Session III was an open seminar focusing on standardization and calibration of radiation monitoring and safety equipment. Radiation safety control and radioactive waste management should be based on the reliable and precise measurement of the quantities such as Dose (Sv) and Radioactivity (Bq) and regular a calibration regime is indispensable in ensuring good measurements. It is also important to make sure that the calibrations are traceable to national standards.

Prof. Kosako, Japan, gave a brief introductory remarks emphasizing on the importance of calibrations and Dr. Harano made an introductory talk on the international circumstances of calibration and standardization relating to ionizing radiation. It was emphasized that accurate measurements are always supported by traceability to national standards by regular calibrations. National standards on ionizing radiation are maintained by a national metrology institute with the other SI units in each country. BIPM-centered international frameworks organize comparison exercises to check worldwide consistency of national standards. ISO/IEC 17025 and international accreditation programs were also presented.

Ms. Lynn Tan, Australia, provided a presentation on personal dosimetry, calibration facility and exposure control measures at the Australian Nuclear Science and Technology Organization (ANSTO). At ANSTO personal dosimetry using TLDs and whole body monitors constitute the official recording and reporting system while EPDs is part of ANSTO 's non-official but equally important dosimetry system. ANSTO has a calibration facility for gamma-rays and neutrons and the reference instruments are calibrated regularly with traceability to national standards of the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), the national metrology institute in Australia. The calibration facility was previously upgraded with new operational and safety features. Exposure control in ANSTO follows closely the principles behind the hazard control hierarchy. Examples of engineering and administrative controls and personal protective equipments were shown in the presentation.

Dr. Moinul Islam, Bangladesh, provided a presentation on the status of the Secondary Standard Dosimetry Laboratory (SSDL) in Bangladesh. SSDL has activities on calibration and standardization of radiation survey meter/pocket dosimeter, ionization chambers and TLDs of different stakeholders in Bangladesh using secondary standard sources of gamma rays, beta-rays, X-rays and neutrons. SSDL has participated in the IAEA/WHO Postal Dose Inter-comparison Program to check the accuracy of output dose measures by SSDL. Environmental and radiation protection activities around the TRIGA Mark-II research reactor (RR) were also shown in the presentation.

Dr. Fan Zhiwen, China, provided a presentation on the objectives of radiation protection, calibration and standardization in China. Calibration is governed by the Metrology Law of the People 's Republic of China. The National Metrology Institute (NMI) and the China Institute of Atomic Energy (CIAE) maintain the national standards on ionizing radiation. The CIRP has a secondary standards calibration laboratory for photon and beta-ray dosimetry and radioactivity in the Department of Radiation Protection and the reference instruments have traceability to the national standards of NMI and CIAE. Dr Fan also reported on the nuclear standards in China. China has approximately 2000 nuclear standards, of which about 400 are on nuclear power plant and more than 140 on radioactive waste management.

Dr. Syahrir, Indonesia, gave a presentation on the status of SSDL Jakarta in Indonesia. SSDL Jakarta, a calibration laboratory established in 1984, is responsible for nuclear radiation metrology in the Centre of Technology for Radiation Safety and Metrology (CTRSM) of the National Radiation Metrology Laboratory (NRML). The irradiation room, sources and reference standards used for calibration were shown in the presentation. Calibration services are in protection and therapy levels to local calibration laboratories and hospitals. The laboratory has actively participated in postal dose inter-comparison service provided by the IAEA on those levels. SSDL Jakarta is planning to obtain ISO/IEC 17025 accreditation involving APLAC MRA program for international recognition.

Dr. Harano, Japan, provided an overview of the status of calibration and standardization of ionizing radiation in Japan. Japan has established a comprehensive system for national metrology in the field of ionizing radiation such as promotion institutions, calibration laboratories, accreditation system, primary standards etc. This system provides good accuracy and reliability. The presentation emphasized the importance of international comparisons and quality control amongst international organizations in the field.

Dr. Wahab, Malaysia, introduced SSDL-Nuclear Malaysia, the national calibration laboratory for radiation measuring instruments for gamma-rays, X-rays, beta-rays and neutrons. More than 1500 radiation instruments are being calibrated each year. SSDL-Nuclear Malaysia is accredited under the Laboratory Accreditation Scheme of Malaysia (SAMM) to meet the requirements of ISO/IEC 17025. Compliance assessment is performed by the Malaysian accreditation body, the Department of Standards Malaysia. From 1985 to 2009, SSDL-Nuclear Malaysia has participated in many international comparisons on dosimetry measurements. For example, the IAEA/WHO International Inter-comparison TLD Postal Dose Quality Audit for Co-60, Cs-237 and Mega voltage x-ray beam, the calibration of ionization chamber under the IAEA program and the inter-comparison program under the Asia Pacific Metrology Program (APMP). SSDL-Nuclear Malaysia also provides personal dosimetry service (film badge and TLD) for more than 17000 personnel in Malaysia. This personal dosimetry service is accredited under ISO 9001:2000 Quality Management system.

Ms. Palattao, Philippines, talked about the status of calibration and standardization of radiation measurements at SSDL in the Philippine Nuclear Research Institute (PNRI). PNRI-SSDL, established in 1974, is maintained by the radiation protection service section of PNRI. PNRI-SSDL provides calibration services for gamma-rays, X-rays and neutrons monitoring instruments and dosimeters. It uses free ionization chambers as reference standards for gamma-rays and X-rays, and AmBe neutron source for neutrons. The PNRI-SSDL participates in dose measurement inter comparisons regularly within the RCA region including the first run of the TLD Audit for radiation protection level dosimetry for SSDLs conducted by IAEA in 2008.

Mr. Vu Manh Khoi, Vietnam, presented on the personal dosimetry and equipment calibration in the Institute of Nuclear Science and Techniques (INST) of the Vietnam Atomic Energy Commission (VAEI). INST has a calibration laboratory for ionizing radiation (SSDL) in the centre for radiation protection and environment monitoring. The laboratory of 11 staff operates the calibration equipment and personal dosimetry systems which monitor for X-rays and gamma-rays using TLD 's. Reference instruments such as the graphite ionization chambers are calibrated regularly by the IAEA. The laboratory also participated in inter-comparison programs. Vietnam plans to introduce a small neutron irradiation facility for calibration purposes. Mr Vu also provided a summary of the status of personal dosimetry in Vietnam.

Also from Vietnam, Mr. Tran Ngoc Toan presented on the development and establishment of the X-ray field for calibration of dosimeters used in diagnostic radiology at SSDL in INST. New radiation quality systems for dosimetry in diagnostic radiology (RQR, RQA and RQT) have been successfully established in line with the international code of practice published by the IAEA.

Also in Session III, a DVD titled "Measurement standards help make the world one" was shown to the participants. The DVD provided information on the metrology system of Japan as well as general useful information on the SI units, national measurement standards, measurement traceability, and the international framework in metrology. Fuji Electric System Co. Ltd. (FES) introduced calibrators and monitoring system manufactured by the company. FES is also a manufacturer of radiation measurement devices such as survey meters, area monitors and personal dose meters. FES operates 4 types of calibrators for gamma-rays, beta-rays and neutrons, with reference standards traceable to the national standards in Japan. This was useful information for the workshop participants.

There were two presentations in Theme 1 - first by Australia, followed by Thailand.

Australia: Waste Operations Radioactive Waste Management Radioactive Waste Management - 5Year Capital Plan

Mr. Lubi Dimitrovski detailed the status of ANSTO 's a radioactive waste management 5 -Year capital plan. The Waste Operations capital projects include the intermediate level waste return, low level solid waste facilities upgrade, a new Mo-99 intermediate level waste immobilsation process, delay and decay facility and a new centralised nuclear materials store. Other 5  Year Plan capital projects such as a new 10 tonne crane, new shielded flask for spent resin, decontamination chamber, expansion of storage for ILSW, upgrade of a spent source storage facility and the drum drying for low level liquid sludges have been completed. Upcoming projects include the strategic consolidation of ANSTO 's radioactive waste to a controlled centralized area. Anticipated completion dates for the new nuclear material store and the delay-and-decay facility are mid 2010 and late 2010 respectively. The capital plan projects will provide ANSTO with increased LLSW storage capacity for a further 20 years at current waste generation rate and also the risk resulting from the ongoing delay in establishing the Australian co-located LILW Repository and ILW Store Facility.

Thailand: Study on Safety Assessment of the Existing Pre-Disposal facilities in Bangkok

Ms. Nanthavan Ya-anant of Thailand presented the preliminary activities undertaken by TINT on the safety assessment of their pre-disposal facilities. Ms. Ya-anan introduced the Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) project led by the International Atomic Energy Agency (IAEA) to specifically address predisposal radioactive waste management issues in a structured manner.

As an offshoot from the 5th plenary meeting that was held in Croatia in June 2008, the Thailand facilities in Chatuchak district in Bangkok were proposed to be a test case under the SADRWMS project. Ms. Ya-anant discussed the SAFRAN tool which was developed to implement the SADRWMS methodology. She elaborated on the various features of the SAFRAN tool, its applicability in predisposal management including the different modules contained in the software. To implement the tool, Ms. Ya-anant prepared a comprehensive report describing the facilities, regulatory framework, waste characteristics as well as the different activities that are being carried out in the facilities. Based on the report, data has been synthesized to suit the requirements of the software. An IAEA Expert Mission has been undertaken early this year to assist this purpose. Further work will be carried out to obtain preliminary results arising from the assessment of the facilities.

Theme 2 of Session IV consisted of two reports presented by Mr. H. Sato and Mr. T. Oumi from Japan.

Mr. Oumi introduced "The recent status of the radioactive waste program in Japan". The decommissioning status of Tokai Nuclear Power Plant and the estimated volume of radioactive waste from the reactor were provided. Dismantlement of equipment was also described in the report. Potential uses of clearance level for metallic wastes were detailed including shielding for accelerator, bench, table, metal block and barrier. The transportation and inspection of radioactive waste in the disposal center was also provided. Mr.Oumi also detailed the recent investigations for the disposal of comparatively high level activity LLW into intermediate depth disposal tunnels.

On the 1st of June 2009, Chubu EPCO applied for the decommissioning of the Hamoka-1&2 nuclear power plants. Decommissioning of Fugen, a domestically developed heavy water reactor which was shut down in 2003 has commenced and is currently in the preliminary dismantling stage. The decommissioning is expected to be completed by 2027.

A geological disposal site has not been found in Japan as yet for HLW. HL Radioactive waste bound for geological disposal is regulated as Class I waste. There is no formal disposal program for research reactors. Radioactive wastes from research reactors and radioisotope production are executed by the Japan Atomic Energy Authority (JAEA). In 1985 the Nuclear Safety Committee (NSC) in Japan set a dose exemption level of 10 µSv/y during their assessment for low level wastes disposal. However in 2009 in close cooperation with ICRP, the new dose constraint of 300 µSv/y was introduced as the safety assessment criterion for low level radioactive wastes.

1. Bach Mai Hospital, Hanoi

FNCA participants arrived at Bach Mai hospital at 9am for discussions and meeting with Assoc. Prof. Mai Trong Khoa (Vice Director of Bach Mai Hospital, Director of the Nuclear Medicine and Oncology Center), Prof. Phan Sy An (former director of the Nuclear Medicine and Oncology Center) and their colleagues. Some of the topics covered included the provision of emergency diagnosis and treatment, training, scientific research, disease prevention and the management of the medical economy. The importance of engaging in international cooperation as well as the role in assisting provincial hospitals to establish guidelines were also discussed.

Bach Mai Hospital (BMH) commenced in 1911 as 'Cong Vong Hospital for Infectious Diseases '. Covering an area of 11.4 hectare, it is Vietnam 's biggest general hospital. In 2007, BMH was given a special ranking as a medical centre and main teaching hospital for Hanoi Medical University. It consists of two institutes, five centers, 21 clinical departments, seven para-clinical departments, eight functional offices and a nursing school. There is a total of 2,000 staff of which 1,800 are hospital staff and 200 are lecturers from Hanoi Medical University. The hospital staff includes 500 doctors and 800 nurses and technicians, with qualifications ranging from professors, associate professors, PhD, Masters and Bachelor degree holders.

Following a presentation by Prof. Mai, the participants visited the Nuclear Medicine and Oncology Center, the Imaging Diagnostic Department and the Cardio Interventional Unit of the Cardio-Vascular Institute. The visit to Bach Mai hospital ended around 11:30am.

2. Training center NUTECH and Calibration Facilities at INST

Participants arrived at the Institute for Nuclear Science and Technology (INST) at about 1:50 p.m for a technical visit. The Institute was founded in 1991 under the Vietnam Atomic Energy Commission. The present director of the Institute, Dr Trinh Van Giap, introduced other members of INST to the FNCA participants.

On behalf of the FNCA participants, Prof Kosako explained the functions and responsibilities of FNCA (RS & RWM) and introduced all of the participants. The participants were then briefed on the function and organization of the institute, followed by a visit through the various facilities within the institute.

At the training center participants were shown and briefed on a variety of radiation monitoring instruments used in the center. These included a gamma spectrometer (hyper-pure germanium detector and NaI (Tl) detector), liquid scintillation counter, gross beta-gamma counter, survey meter equipment (GM survey meter, sodium iodide survey meter, neutron detector, ionization chamber survey meter and plastic scintillation survey meter) and TLD readers. Participants were also briefed on the training program on scatted radiation and attenuation factor.

The next area visited was the TLD Laboratory where INST provides individual monitoring services to radiation institutions in Northern Vietnam. Participants visited the calibration rooms including three exposure bunkers housing calibration instruments for gamma and x-rays.

The final area visited was the cyclotron facility which was recently commissioned by the Institute. The facility consists of a cyclotron machine, a hot cell room and a preparation and quality control room. At present, the Institute produces only fluorine (F-18), an isotope used by hospitals in nuclear medicine for diagnostic purposes.

There were four presentations including one DVD presentation in Session V.

Dr. Le Chi Dung, Vietnam, informed the participants of the radiation protection aspect of Vietnam 's first nuclear power plant (NPP), detailing the Atomic Energy Law which strictly follows the IAEA documentation structure and guidelines. The schedule for developing Vietnam 's the first nuclear power plant has been set and is planned to be operational by the year 2020. The need to develop a radiation safety infrastructure for the NPP program is also under ongoing review.

Dr. Nguyen Ba Tien updated the participants on Vietnam 's radioactive waste management status. In support of the government 's program for the country 's first NPP, a review of the current radioactive waste management system in Vietnam is in progress. Radioactive waste disposal activities have been initiated and three potential sites have been preliminarily selected for near surface radioactive waste disposal.

A DVD illustrating Japan 's experience during the early development of NPP in the country was presented by Mr. T. Oumi, Japan. Japan has since had extensive experience in the development and operation of several types of NPPs, including BWRs and PWRs.

Mr. T. Oumi, also introduced the historical development of radiation protection and radioactive waste management in Japan 's NPPs. The personnel dose management system has improved greatly, through ongoing continuous improvement to monitoring systems.

Session V consists of three reports presented by Malaysia, Australia and Philippines.

Malaysia: Radiation Safety at Reactor TRIGA PUSPATI (RTP) in Malaysia

Dr. Wahab, Malaysia described the implementation of a radiation safety program at the TRIGA PUSPATI (RTP) Reactor. Dr Wahab introduced the staff involved in the operation of the reactor and explained the reactor type and fuel elements used. The reactor building was constructed in November 1981 and reached its first criticality on 28 June 1982. The Safety, Health and Environmental Management System (SHE-MS) in Nuclear Malaysia was established in 2005 with a very comprehensive policy put in place. The SHE-MS was revised in 2007 to provide a more effective operational and safety system. The first safety analysis report (SAR) for RTP was completed in 1982. In 2008, the SAR was revised and approved by the Atomic Energy Licensing Board (AELB). Management at Nuclear Malaysia sets a high priority for emergency preparedness and response program. Any changes in the operation and maintenance of the reactor must be approved by the reactor supervisor. If a new application is introduced into the routine operation, approval by the Reactor Manager must be obtained. A radioactive waste management program is in place and education and training program for safe operation of RTP are regularly conducted by Nuclear Malaysia. This is certified by AELB. There is no spent fuel at Nuclear Malaysia at present. Nuclear Malaysia is committed to always maintaining, improving and strengthening safety within its organization.

Australia: Radiation Safety Aspects of Decontaminating High Activity Hot Cells

Ms. Lynn Tan, Australia, presented on the radiation safety aspects of decontaminating hot cells. ANSTO has completed decontaminating 5 hot cells which were used for the acidic processing of Mo-99 over the past 25 years. The high radiation and contamination levels in the cells (20  850 mSv/h and gross beta > 10,000 Bq/cm2) require extensive planning be carried out in order to manage the exposure and containment related issues for staff and the environment. Equipment such as manipulators, pneumatic cutters, nibblers, wireless CCTV camera and monitors, were employed during the remote cleanout. Contaminated items such as the liquid waste tanks, tray tables and floor plates were removed from the cell to the waste storage area using shielded flasks. Once all the equipment had been removed, in-cell decontamination using strippable paint and mild acid was carried out. Air lock tents, portal monitor, hand and foot monitor, whole body counting and appropriate personal protection equipment were used as part of the contamination control.

Ms. Tan emphasized the importance of quick and efficient handling and removal of appropriately packaged waste items to prevent dose build up in work areas. Proper documentation of the dose rates and contamination levels of wastes should also be provided to assist downstream processing of the waste items. It was a successful decontamination operation with both individual and collective doses well below the set dose constraints. Careful assessment and coordination throughout the program was found to be very important in this type of decontamination program. Clear distribution of tasks amongst workers according to capabilities reduced unnecessary dose exposures. Achieving ALARA through dose sharing was found to be effective. Other lessons learnt included the need for proper packaging, removal and storage of waste, identification and removal of shielding of sources and the management of other risks such as fatigue, confined space and working at heights.

Philippines: Radiation Monitoring and Control of a Thorium Contaminated Building: Preliminary Results

Ms. Palattao advised that the PNRI is currently evaluating the release of a thorium gas mantle manufacturing plant from regulatory control. As required by the regulations, the facility must be free from any contamination and suitable for unrestricted use. For this purpose, preliminary radiation monitoring of the facility has been conducted to determine probable contamination including radioactive gas releases to the environment. An online gas monitor, Durridge RAD7 instrument preset at 5 minute sniff mode was used to measure ambient thoron in strategic places. Soil and sediment samples were collected and analyzed for 232Th and progenies content using a Wallac (Perkin Elmer) liquid scintillation counter. The samples were collected from the drain, p-trap and outside canal. Highest thoron levels were found in the mantle processing and packaging section, and knitting room (396-3930 Bq/m3).High concentrations of 232Th and progenies were measured in sediments collected from the outside canal and under the drain, with concentrations of 59.9 and 36.1 Bq/m3 respectively. Continual efforts is still needed to complete the tasks which include detailed monitoring of the whole building, boring and sampling of concrete inside the building. Collection and analysis of additional environmental samples around the plant will also be required. If necessary, facility clean up and soil remediation from the affected areas around the plant will be carried out prior to release from regulatory control.

Session VI involved a roundtable discussion and updates by each country 's Project Leader on the status of involvement and participation in current and future cooperation with other international programs such as the IAEA/ANSN and RCA/RAS9042 programs. A summary of the comments by the Country Project Leaders are detailed below.

Mr. Sato also highlighted the IAEA 's involvement in the area of radiation safety including training programs. He also outlined the numerous activities the ANSN has been involved in including organising a workshop on "Disused Sealed Radioactive Sources" held in Chiang Mai, Thailand in 10-14 January 2009. Also planned for 2009 is an ANSN Topical Group meeting on Radioactive Waste Management in October 2009.

The status of the borehole technology system for disused source disposal (BOSS) was also discussed by the Country Project Leaders. The IAEA has produced a technical document on the BOSS disposal system and is actively pursuing the installation of the first BOSS system in Ghana. There is still an evident lack of progress worldwide on the BOSS system for the disposal of disused sealed sources.

Dr. Fan also provided a forward plan aimed at enhancing the current successes and benefits that the FNCA and ANSN program activities provide and deliver. These include continual exchange of technical information and discussion on common themes specific to the Asian region. Stability of the human and financial resources to the Asian region is also important, and this includes the provision of expertise in areas such as disused source disposal and NORM issues.

The Philippines also participates in the RCA project RAS/9042 on Sustainability of Regional Radiation Protection Infrastructures. RAS/9042 promotes sustainability of radiation protection infrastructures through a number of activities, including the establishment of a dynamic and active regional networking with exchange of information and continued mutual support of regional radiation protection initiatives. The RCA project has four components covering regulatory infrastructure (including public exposure control), occupational exposure control, medical (patient) exposure control, and radiological emergency preparedness and response. Philippines hosted the mid-term review meeting in February 2009. It also hosted the Technical Meeting of the Regulators Forum on Regional Priority Issues and Solutions on 5-7 August 2008. The RCA Regulators Forum Steering Committee is composed of Philippines (Chair), Australia, India, Malaysia and Vietnam. Australia and Indonesia were designated administrators that will assist the Committee.

Australian technical experts also attended the ANSN Topical Group Meeting on Safety Management of Research Reactors - SMRRTG (May 21-22 in Hanoi). The SMRRTG have agreed to adopt a working methodology to improve both Human and Information Technology networks.

Australia is also supporting in other regional cooperation activities including the FNCA RS & RWM workshops and other ANSN programs.