Kajian pembentukan peraturan mengenai sistem pendingin reaktor dan sistem terkait untuk reaktor berpendingin gas

IN 2021, BAPETEN, AS THE REGULATORY BODY, IS ESTABLISHING A BAPETEN REGULATION REGARDING THE REACTOR COOLANT SYSTEM AND RELATED SYSTEMS, WHICH CURRENTLY ARE NOT YET AVAILABLE. Therefore, it is crucial to establish the BAPETEN Regulation. Based on the reasons, before setting the BAPETEN Regulation, it is necessary to conduct a study that is expected to provide a more comprehensive description and provide recommendations on what things need to be regulated in the BAPETEN Regulation, especially for gas-cooled reactors. The method used in this study is a literature study from various relevant references. The result of this study is that it is essential to require a capacity of the ultimate heat sink, including the spent nuclear fuel storage pool and a minimum period of the ability of the top heat sink in the accident analysis if the decay heat in the storage pool and the residual heat in the reactor core fail simultaneously. On the other hand, it is also necessary to require a margin of uncertainty to evaluate a situation and take corrective action. Likewise, independent and redundant access to the ultimate heat sink is needed to increase reliability. As for gas-cooled reactors, it is required to adapt the terms used. In addition, it is necessary to determine the appropriate definition because some of the terms used in water-cooled reactors have the same terms as gas-cooled reactors but have different functions. Keywords: Regulatory assessment, coolant system, related systems, gas-cooled reactors

Kajian pemantauan dosis neutron terhadap pekerja radiasi pada pengoperasian Linac dengan energi foton ≥ 10 MV

The use of Linac for radiotherapy is starting to use a lot of high-energy photons of 10 MV; in addition, some use 15 MV for patient therapy in routine use, there is also the use of 6 MV. The purpose of this study is to obtain an overview and information of the neutron dose that has the potential to provide additional doses for radiation workers operating the Linac 10 MV aircraft. Based on the Regulation of the Head of BAPETEN No. 3 of 2013, Article 48 paragraph (2) states that in the operation of Linac with X-ray photon energies above 10 MV, must coat the shield wall with a neutron-absorbing material. The statement follows the IAEA-TecDoc 1891 that neutrons will have the potential to have a significant radiological impact on workers if routinely operated at energies above 10 MV, so must consider protection for workers. The results of a survey from 27 hospitals, obtained information through filling out questionnaires and discussions and validated with B@LIS Pendora, it found that the trend of annual doses received by each profession in the operation of Linac 6 MV, 10 MV, and 15 MV was less than one mSv, only partially small worker dose that is above one mSv (above the 90th percentile). This study concluded that the presence of neutrons in Linacs up to 10 MV was deemed not to have a significant radiological impact on workers. The recommended criteria/mechanism for monitoring worker neutron doses in Linacs up to 10 MV could be based on if the safety study results obtained a dose received by workers 1.5 mSv/year. Then, there is no need to monitor the neutron dose. If the measurement results of exposure to neutron and gama radiation around the Linac space are 7.5 microSv/hour, there is no need for neutron monitoring. In Linacs above 10 MV, if the annual effective dose is 1.5 mSv/year, there is no need to monitor the dose of special neutron personnel. Still, routine radiation exposure monitoring may be considered every two years. Keywords: Neutron Dose, Radiation Worker, Linac, Dose Monitoring.

Tinjauan peraturan keselamatan utilisasi dan modifikasi instalasi nuklir nonreaktor

The service life of Non-Reactor Nuclear Installations (INNR) in Indonesia is quite long, so it is essential to make modifications. In addition, developments of technology and market demand with the products could modify INNR, such as replacing and adding a control system to interim storage of nuclear-spent fuel facility (KHIPSB3) [1]. Due to the absence of technical regulations related to the modification and utilization of the new INNR and to provide uniformity of format and content in carrying out the further utilization and modification of the INNR, it is necessary to study the literature, compare regulations and consult with resource persons. From the results of these studies and consultations, an overview and solution of arrangements before, during, and after the new utilization or modification of INNR are obtained, making it easier for permit holders or evaluators to carry out activities related to the further utilization or modification of INNR. From the review results, we can conclude that special regulations related to the safety of new utilization or modification of INNR need to be issued immediately by the regulatory body. This review is expected to be a reference in making regulations for the further utilization and modification of INNR, which regulates the format and content of the modification or new utilization of INNR, which becomes a guideline for licensee and evaluators in implementing further utilization and modification of INNR. Keywords: modification, utilization, INNR

Pengembangan spesifikasi teknis sistem pemantau radiasi lingkungan berbasis spektrometer gama untuk pengawasan ketenaganukliran di Indonesia

THE INDONESIAN RADIATION DATA MONITORING SYSTEM (IRDMS) IS A NETWORK CATEGORIZED AS COMPLEX PROBLEMS WITH INFLUENCING FACTORS INTO A SINGLE UNIT AS MULTIPLE PROBLEMS THAT MUST SOLVE THROUGH VARIOUS APPROACHES OPTIMALLY. One of the approaches required is the application of optimization. For example, optimization is needed between the detection sensitivity of the radiation source and the number of false alarms due to the permissible background radiation by determining the operating parameters of the monitor. In addition, optimization is needed between costs and data (information) obtained through determining the influencing factors in establishing a monitoring base, namely the purpose of installation at the location (safety and security), demographics, legal subjects, resources, type (technology) detectors, and environmental radioactivity. To increase the national content for the use of the product, the problem statement of this paper focuses on developing technical specifications for the type of low-resolution gamma spectrometer-based monitor (detector) following the analytical method developed by the authors for the determination of alarms triggered by radiation from facilities and equipment. This study aims to develop IRDMS technical specifications following the needs of nuclear control and bridge the gap (transition) of acceptance of national content before the parties can accept it as SNI. This proposed technical specification was adopted from the international standard IEC 61017:2016 and modified to suit the proposed alarm determination analysis method and Indonesian conditions, including consultation with interested parties. The content of this technical specification is relatively broad in scope. It is hoped that it can be adopted by parties who must carry out environmental monitoring following regulatory criteria and with the ability to provide alarms by increasing radiation doses equivalent to natural events (especially by rain). Keywords: environmental monitoring, gamma spectrometer, regulatory oversight, early warning

Usulan kriteria pemulangan pasien (patient release) kedokteran nuklir di Indonesia

Nuclear medicine procedures are carried out by applying a radioactive substance to the patient’s body. Thus, the patient can be assumed to be a ‘radiation source’ and needs to follow special provisions so that his presence does not expose nearby individuals unnecessarily. Therefore, when the patient is released from the hospital, it must ensure that the patient’s radiation exposure does not expose the individuals in the vicinity. However, several related regulations have not regulated this in detail. In this paper, a study is carried out regarding the criteria considered in the release of nuclear medicine patients. The method used is a literature study. The study results recommend release criteria through two approaches based on the estimated maximum effective dose that the public may accept, namely conditional release with a calculated dose of less than or equal to 5 mSv and unconditional release with an estimated dose of less than or equal to 1 mSv. Conditional release is the release of a patient provided with post-release guidance, while unconditional release is the release of the patient without being supplied with post-release advice. Keywords: nuclear medicine, patient release, conditional release, unconditional release

Studi komparasi GSR Part 2 dan ISO 45001:2018

Government Regulation Number 54 the Year 2021 regarding Safety and Security of Nuclear Installations requires the licensee to establish and implement a safety and security management system for nuclear installations. Currently, a revision is being made to Bapeten Chairman Regulation No. 4 the Year 2010 regarding the Management System for Facilities and Activities of Nuclear Energy Utilization following GSR Part 2 issued by IAEA as the latest guideline for the nuclear safety management system. On the other hand, the industrial world is familiar with the occupational health and safety management system (OHSMS), which was once popular with the OHSAS 18001 series and has now been migrated to ISO 45001. Therefore, a study was conducted to examine the clauses in ISO 45001:2018 as the latest international OHSMS standard that can meet the requirements in GSR Part 2. The study results concluded that the clauses in ISO 45001:2018 could meet most of the provisions contained in GSR Part 2. However, several other parts still need to be added, namely the expansion of the fundamental objectives of the management system to include public and environment, development of the scope of resources to include funding, demonstration of safety leadership to each manager, and explanation of the implementation of safety culture. Keywords: Management System, GSR Part 2, ISO 45001:2018, Occupational Health and Safety.

Identifikasi kebutuhan sarana-prasarana pemantauan radiasi nirawak dalam pengawasan radiasi reaktor riset di Indonesia

The facility’s licensee conducts environmental radiation monitoring in nuclear facilities to monitor radiation exposure in the facility’s vicinity. This activity is carried out also to monitor radiation release as a result of nuclear reactor operation. Aside from that, monitoring also works as a device to monitor radioactive release in a nuclear emergency. Therefore, the radiation monitoring system is crucial in nuclear utilization facilities to determine the number of radiation exposure to the surrounding environment. However, the existing stationary monitoring system has a risk of being unable to work if the system is down in case of natural disaster occurs. One way to mitigate this risk is to deploy an unmanned radiation monitoring system to monitor radiation exposure without putting personnel at risk. To define a suitable unmanned radiation monitoring system, identification of facilities and infrastructure required to design an unmanned radiation monitoring system for a research reactor in Indonesia is carried out. Facilities and infrastructure needed for unmanned radiation monitoring systems are unmanned aerial vehicles, radiation detector, control and communication module, navigation system, and software for the control system. These required facilities and infrastructure are then specified to determine the necessary specification for monitoring research reactor in Indonesia. The facilities’ required specifications are unmanned aerial vehicles with rotary-wing type, CdZnTe Detector, and GPS/GLONASS based navigation system. For infrastructure specification, control and communication module and software for the control system is not specified in how the system could meet the expected required performance rather than in detail. However, the system must provide and process measurement data in real-time to be presented in a radiation heatmap. Keywords: Identification, Radiation Monitoring, Unmanned

Telaah Singkat Kebijakan Akreditasi Bagi Lembaga Uji Kesesuaian Pesawat Sinar-X

Brief Review of Accreditation Policy For X-Ray Compliance Testing Laboratory The Compli¬ance Test Program has been Implemented Since 2011 and The Updated Regulation was in 2018. According to the implementation progress, adjustments are needed to the dynamics of the problems that arise. In 2021, it is planned to prepare a draft amendment to BAPETEN Regulation Number 2 of 2018; therefore, an analysis of the implementation profile of the regulation is carried out to identify existing obstacles. One of the problems identified is the polemic of the urgency of accreditation obligations for the Compliance Testing Laboratory, which is the institution appointed by the Head of BAPETEN to carry out compliance tests and issue compliance certificates. Currently, 78% of laboratories are not accredited, most of which are importing companies. Therefore, it will have implications for reducing laboratory availability and constraining the compliance test process in health facilities. This paper aims to identify aspects that can hinder the application for laboratory accreditation, especially for importing companies, and the proposed solution that can recommend. This paper uses a regulatory impact analysis approach. The study results show that laboratory accreditation is essential to maintain the quality of services, competencies, and outputs of the laboratory so that four options that LUK can take are proposed in dealing with obstacles in applying for accreditation. This paper can provide contributions in preparing the draft amendments to BAPETEN Regulation Number 2 of 2018.

Studi Paparan Radiasi pada Pekerja Radiasi Cathlab dengan Menggunakan My Dose Mini sebagai Upaya Keselamatan Radiasi di RSUP Adam Malik Medan

Cathlab radiation workers, when performing interventional procedures, are at high risk of the effects of radiation exposure. The risk of radiation exposure is deterministic and stochastic biological effects. Therefore, radiation exposure studies of radiation workers at the cath lab were conducted to determine the value of radiation exposure received. This radiation exposure study was conducted by measuring and recording radiation exposure doses received by radiation workers. Measurements are made when the radiation officer performs the intervention procedure. The research was carried out for one month in the cath lab room of the Adam Malik General Hospital, Medan. The modalities used are GE Medical System Interventional Fluoroscopy and Phillips Allura Xper FD20. The dosimeter used is “my dose mini”, which is placed inside a shield or apron worn by radiation workers. The size of the apron shield used is 0.50 mm Pb at the front and 0.25 mm Pb at the rear. Radiation officers whose radiation exposure dose was measured consisted of 10 doctors, 11 nurses, and one radiographer. Each inspection procedure of each radiation worker has a different distance, time, and shield from the radiation source. The measurement of radiation exposure dose is (1-59 μSv) for doctors, (1-58 μSv) for nurses, and 1 μSv for radiographers. To protect against radiation must pay attention to the factors of time, distance, and shielding. Ways that can do are to avoid being close to radiation sources for too long, keep a space at a safe level from radiation, and use shields such as Pb-coated aprons, use Pb gloves, Pb goggles, and thyroid protectors. The amount of radiation exposure dose received by each radiation worker at the time of measurement is still within the tolerance limit. The Nuclear Energy Regulatory Agency (BAPETEN) regulation, which the International Commission recommends on Radiological Protection (ICRP), is 20 mSv/year. The results of this study are expected to be used as input for improving the quality of service for monitoring radiation exposure doses in the Cathlab and as reference material for further research.

Dilematika dan Tantangan Pengawasan Nuklir di Masa Pandemi COVID-19

Dilematics and Challenges of Nuclear Regulatory Control During the Pandemic of Covid-19. Any activity using nuclear energy must be controlled by the Nuclear Energy Regulatory Agency (BAPETEN). The regulatory control is aimed at protecting the health and safety of working personnel, public and environment from the potential hazards arising from nuclear activities. In the implementation of regulatory control, it often needs to do activity involving a number of people, such as meeting to discuss regulation or to clarify some issues of licensing. In many cases, it needs also to do licensing verification and regulatory inspection to the nuclear/radiation facilities to ensure their safety conditions. However, since the outbreak of COVID-19, activities that involve many people such as meetings and visits must be reduced. This has created some regulatory dilemmas and challenges. Therefore, it is necessary to conduct a study to analyze these dilemmas/challenges to find their solutions. Present study using analytical descriptive method was performed to answer such problems. This paper presents results of the study in the form of analysis of the regulatory dilemmas/challenges, and recommends some solutions.¬