Nuclear Power Supervisory Regulation Number 4 By 2013

Original Language Title: Peraturan Badan Pengawas Tenaga Nuklir Nomor 4 Tahun 2013

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Read the untranslated law here: http://peraturan.go.id/inc/view/11e44c50cc8d7ad08a30313233313034.html

BN 715-2013 fnHeader (); The text is not in the original format.
Back NEWS REPUBLIC of INDONESIA No. 672, 2013 SUPERVISORY NUCLEAR POWER. Radiation Protection. Salvation. Utilization. Nuclear. Repeal.

REGULATION of NUCLEAR POWER WATCHDOG AGENCY HEADS of the REPUBLIC of INDONESIA number 4 2013 ABOUT RADIATION PROTECTION and SAFETY in the UTILIZATION of NUCLEAR ENERGY with the GRACE of GOD ALMIGHTY HEAD of AGENCY PENGAWA NUCLEAR POWER the REPUBLIC of INDONESIA, Considering: a. that in order to implement the provisions in article 6 paragraph (6), article 17 paragraph (3), article 20, article 10 paragraph (3), section 23 subsection (4), article 25 paragraph (3) and article 31, paragraph (4) the Government Regulation Number 33 in 2007 about the safety of ionizing radiation and Radioactive Source Security;
b. that the provision of Safety Against radiation is regulated in the decision of the head of the nuclear power Watchdog Agency number 01/Ka-BAPETEN/V-100 is no longer appropriate to the needs of the legal community, the prevailing international standards and development of science and technology in the utilization of ionizing radiation Sources so that needs to be replaced;
c. that based on considerations as referred to in letters a and b have to set the rules of the nuclear power Supervisory Head of Radiation Safety in the protection and the utilization of nuclear power;
Remember: 1. Act No. 10 of 1997 of Ketenaganukliran (State Gazette of the Republic of Indonesia Number 23 in 1997, an additional State Gazette Number 3676);
2. The Government of the Republic of Indonesia Number 43 in 2006 about Licensing of nuclear reactors (State Gazette of the Republic of Indonesia Number 106 in 2006, an additional State Gazette Number 4668);
3. The Government of the Republic of Indonesia Number 33 of 2007 about the safety of ionizing radiation and Radioactive Source Security (State Gazette of the Republic of Indonesia Number 74 in 2007, an additional State Gazette Number 4730);
4. The Government of the Republic of Indonesia Number 29 in 2008 about Licensing the utilization of ionizing radiation Sources and Nuclear Materials (State Gazette of the Republic of Indonesia Number 54 in 2008, an additional State Gazette Number 4839).
Decide: define: REGULATION of NUCLEAR POWER SUPERVISORY HEAD of RADIATION SAFETY and PROTECTION in the UTILIZATION of NUCLEAR POWER.
CHAPTER I GENERAL PROVISIONS article 1 in regulation Supervisory Chief of nuclear power, which is: 1. the nuclear energy Supervisory hereafter BAPETEN is in charge of carrying out the supervision agencies through regulation, licensing, and inspection of all activities of the utilization of nuclear power.
2. Utilization is an activity related to nuclear power that includes research, development, mining, manufacture, production, transport, storage, diversion, export, import, use, decommissioning, radioactive waste management and to improve the people's welfare.
3. Nuclear power is the energy in any form that were released in the process of transformation of the core, including the energy derived from sources of ionizing radiation.
4. The Radiation Protection Act is being made to reduce the influence of the radiation damage resulting from radiation exposure.
5. The Radiation Safety is actions taken to protect workers, members of the public, and the environment from the hazards of radiation.
6. The holder of the permit is the person or entity that has received the permission of nuclear power Utilization of BAPETEN.
7. Protection of radiation Officers are officers appointed by the holder of the permit and is able to carry out the stated BAPETEN by work-related Radiation Protection.
8. Radiation Worker is any person who works at a nuclear installation or installation of ionizing radiation which is expected to receive annual Doses exceeding the dose for the general public.
9. The radiation safety of the Organizers are those individuals, organizations, the Commission and/or the Committee tasked to assist the holder of the permit in the exercise of responsibilities in the field of Radiation protection and Safety.
10. The recording is a document stating results achieved or provide evidence of implementation of activities in the utilization of nuclear power.
11. Radiation Exposure is the Radiation received by a very human or material, whether intentional or not, that come from internal Radiation or Externa.
12. Exposure to the work is the radiation exposure received by Radiation Workers.
13. Normal Exposure is exposure to radiation that is expected to be received in the condition of normal operation of a facility or installation, including minor accidents that can be controlled.
14. the Potential Exposure is exposure to Radiation that is not expected or predicted but have had a possibility to occur due to accidents or because of an event or series of events that may occur include equipment failure or operating fault.
15. Medical Exposure is exposure to Radiation received by the patients as part of a diagnosis or medical treatment, and others as a volunteer who helped patients.
16. the next dose Limit value of abbreviated NBD is the largest Dose permitted by acceptable BAPETEN by Radiation Workers and community members in a specific time period without causing genetic and somatic effects of meaning due to the utilization of nuclear power.
17. Dose of Radiation Dose is hereinafter referred to as the amount of radiation found in the radiation field or the amount of radiation energy absorbed or accepted by the material kind.
18. The limiting Dose is the upper limit Dose Radiation Workers and community members should not exceed the limit value of the dose used in the optimization of radiation protection and Safety for any utilization of nuclear power.
19. the Equivalent Dose is the dose quantities used in Radiation Protection specific to state the magnitude of the level of damage to the tissues of the body due to terserapnya a number of energy radiation weighting factor to pay attention to the radiation that affected it.
20. The effective Dose is the Dose quantities used in Radiation Protection specific to reflect the risk associated the dose, whose value is the sum of the Equivalent Doses received multiplication network with weighting factors of the network.
21. The Control Area is an area of work that requires action and the provisions of the special safety protection to control Normal Exposure or prevent the spread of contamination during normal working conditions and to prevent or limit the level of Potential Exposure.
22. The supervision Area is the work area outside the control of Areas that require review from exposure to work and does not require action or provision of special safety protection.
23. Contamination is the presence of a radioactive substance shaped solids, liquids, or gases which are not necessarily on the surface of materials, objects, or in a room and inside the human body, which can cause hazard exposure to radiation.
24. Abnormal Conditions are conditions that deviate from normal operating conditions are not expected to occur but did not cause damage to the tools which means influence on Radiation Safety that triggered the accident.
25. The inspection is one of the elements of the supervision of the utilization of nuclear power that is exercised by the Nuclear Safety Inspectors to ensure conformity with these regulations ketenaganukliran.
Article 2 this Regulation the head of BAPETEN set about Radiation protection and Safety in the utilization of nuclear energy which includes Radiation Safety, in charge of the implementation of the requirements of the Radiation Protection, and safety and radiation protection programs in the utilization of nuclear power.

CHAPTER II in CHARGE of RADIATION SAFETY of article 3 (1) the person in charge of the Radiation Safety as stipulated in article 2 include the following: a. the holder of the permit; and b. the personnel associated with the implementation of the utilization of nuclear power.
(2) personnel related to the implementation of the utilization of nuclear energy as stipulated in paragraph (1) as follows: a. the officer Radiation Protection;

b. Radiation Workers; and/or c. the parties got the special responsibility of the holder of the permit.
Article 4 (1) the holder of a permit referred to in article 3 paragraph (1) letter a is responsible for the protection and safety of Radiation at the facility or installation that includes: a. realizing the goal of Radiation Safety;
b. devise, develop, implement, and document the safety and radiation protection programs, based on the nature and risk for each execution of the utilization of nuclear power;
c. form of Radiation Safety Organizer and set within the facility or installation in accordance with the duties and responsibilities;
d. determine the actions and resources needed to achieve the objectives referred to in letter a and ensure that resources are adequate and the action taken can be carried out correctly;
e. review its every action and resources regularly and continuously to ensure the attainment of the goal of Radiation Safety;
f. identifying any failings and weaknesses in the actions and resources needed to realize the safety of radiation, as well as taking steps to repair and prevention of the recurrence of the situation;
g. create procedures to facilitate consultation and cooperation between all parties concerned with Radiation Safety; and h. creating and maintaining the recording that's associated with the Radiation Safety.
(2) the holder of the permit, in carrying out the responsibility referred to in subsection (1) may delegate to the personnel associated with the implementation of the utilization of nuclear energy as stipulated in article 3 paragraph (2).
(3) a Delegation referred to in subsection (2) does not absolve the holders permission from legal liability if there is a situation that could endanger the safety of Radiation Workers, community members, and the environment.
Article 5


Radiation Safety objectives referred to in article 4 paragraph (1) letter a is realized by means of: a. provide: 1) facilities and/or equipment in accordance with the nature and risks of nuclear power Utilization for each; and Radiation Protection gear 2) in accordance with the nature and the risk for any utilization of nuclear power. b. embodies a culture of safety at the facility or installation of nuclear power Utilization;

c. limit Exposure to any Radiation Workers;
d. optimize the protection and safety of Radiation in the utilization of nuclear power; e. implement the health monitoring for Radiation Workers;
f. enhancing the qualifications of a radiation Worker in understanding and applying safety and Radiation Protection through education and training; and g. provide and update information on Radiation safety and Protection to the Workers to radiation.
Article 6 (1) organizers of the Radiation Safety was formed and assigned by the holder of the permit referred to in article 4 paragraph (2) Letter c can consist of: a. those individuals; or b. organizations, commissions, and/or Committee within the structure of the management of the holder of the permit.
(2) a Radiation Safety Providers those individuals referred to in subsection (1) the letter a can be assumed by the Radiation Protection Officer.
(3) the scope of the task, position, and arrangement of the organizers of the Radiation Safety as mentioned in subsection (1) is adapted to the nature and the risk for any utilization of nuclear power.
Article 7 of the Radiation Protection Officer referred to in article 3 paragraph (2) letter a responsibility: a. supervise the implementation of the programme of safety and radiation protection;

b. review of the effectiveness of the implementation of the programme of safety and radiation protection;
c. provide technical and administrative instructions orally or in writing to Workers about Radiation Protection and safety program implementation of radiation; d. identify the needs and organizing training activities;
e. ensure the availability and feasibility of Radiation Protection equipment and monitoring its use; f. creating and maintaining the recording of doses received by Radiation Workers;
g. report to the holder of the permit if the worker received a dose of radiation exceeding the limiting Dose; h informing Workers about Radiation dose monitoring evaluation results;

i. create documents related to Radiation Protection;

j. perform access control in the area of the control.

k. administer countermeasure exercises and fact finding in case of emergency.
b. consultations related to Radiation safety and Protection in the installation.
Article 8 (1) Radiation Worker referred to in article 3 paragraph (2) letter b have a responsibility: a. adhere to operating procedures;

b. follow the health monitoring and monitoring of individual doses;
c. the following education and training to improve the skills and understanding in Radiation safety and Protection;
d. individual dose monitoring apparatus and radiation protective equipment in accordance with the utilization of nuclear power;
e. inform the holder of the permit of a previous work history and current affairs related to radiation; and f. deliver Radiation Protection Officers to input about the constraints and situations that affect the implementation of safety and radiation protection programs.
(2) the provisions regarding the responsibility of the Radiation Worker referred to in subsection (1) for each type of utilization of nuclear power is regulated in the regulations the head of BAPETEN.
Article 9 (1) education and training concerning Radiation safety and Protection as stipulated in article article 5 letter f at least include the following: a. legislation in the field of ketenaganukliran;

b. Resources used in the utilization of nuclear power;

biological radiation effects c.;

d. the quantity and unit of radiation dose;

e. principles of Radiation safety and Protection;

f. monitoring of radiation exposure; and g. the action in an emergency.
(2) scope, type, and duration of the training program tailored to the utilization of nuclear power.
CHAPTER III APPLICATION of the RADIATION PROTECTION REQUIREMENTS of Part One General article 10 Permit holders are obliged to implement the requirements for Radiation Protection in the utilization of nuclear energy, which includes: a. justification;

b. dose limitation; and c. optimization of protection and safety of radiation.

The second part of the Justification of article 11 (1) Justification as mentioned in article 10 the letter a should be based on the principle that the benefits to be gained outweigh the risks posed.
(2) Justification referred to in subsection (1) came into force with regard to factors that include the following: a. the existence of application of other technologies where the risks posed are smaller than other types of nuclear power utilization of previously existing; b. Economic and social;

c. health and safety; and d. the management of radioactive waste and decommissioning.
Article 12 the head of BAPETEN can issue bans for a type of nuclear power Utilization in terms of the principle of justification referred to in article 11 are not met.

The third part of article 13 limitations of Dose Limitation Doses as mentioned in article 10 the letter b is obliged by the holder of the permit through the application of a limit Dose.

Clause 14 of the Dose Limit Value as stipulated in article 13 applies to: a. a radiation Worker;
b. apprentice workers for job training, student, or a student aged 16 (sixteen) years up to 18 (sixteen) years; and c. members of the community.

Article 15 the value Limit doses to Radiation Workers as stipulated in article 2 letter a is assigned to the provisions of: a. the average Effective Dose of 20 mSv (the twenty-milisievert) per year in the period of 5 (five) years, so Dose that accumulates in 5 (five) years may not exceed 100 mSv (one hundred and milisievert); b. the effective Dose of 50 mSv (fifty milisievert) within 1 (one) year;
c. Dose Equivalents for lenses of the eyes of an average of 20 mSv (the twenty-milisievert) per year in the period of 5 (five) years and 50 mSv (fifty milisievert) within 1 (one) year; d. Dosage Equivalent to skin of 500 mSv (1 milisievert) per year; and e. a dose Equivalent to the hand or foot of 500 mSv (1 milisievert) per year.
Article 16 Dose Limit value of apprentices for job training, student, or a student aged 16 (sixteen) years up to 18 (sixteen) years referred to in Article 2 letter b set with conditions: a. the effective Dose of 6 mSv (six milisievert) per year;

b. a dose Equivalent to the lens of the eye of 50 mSv (fifty milisievert) annually;
c. Dose Equivalents for the skin of 150 mSv (one hundred and fifty milisievert) annually; and d. a dose Equivalent to the hand or foot of 150 mSv (one hundred and fifty milisievert) per year.
Article 17 in case of worker apprentice for job training, student, or students aged over 18 (sixteen) years, imposed the same Dose Limit Value with the value of the limit of a defined Dose for Radiation Workers.

Article 18 in the event of Radiation Workers received doses exceeding 20 mSv (twenty milisievert) in 1 (one) year but less than 50 mSv (fifty milisievert), then the holder of the permit should be: a. review radiation exposure and to take corrective measures that are necessary;
b. limit the effective dose of Radiation so that the Workers in question within a period of 5 (five) years old may not get effective dose of 100 mSv (one hundred and milisievert); and c. reported the incident to BAPETEN with include the occurrence and causes of the occurrence of any corrective action that has been carried out.
Article 19 in terms of Radiation Worker received a dose exceeding 50 mSv (fifty milisievert) in one particular year, then the Permit Holder must: a. review radiation exposure and to take corrective measures that are necessary;
b. limit the effective dose of Radiation so that the Workers in question within a period of four (4) years ahead should not obtain effective dose of 50 mSv (fifty milisievert); and c. reported the incident to BAPETEN with include the occurrence and causes of the occurrence of any corrective action that has been carried out.
Article 20 For a Radiation Worker received a dose exceeding 50 mSv (fifty milisievert) less than one year, in addition to a requirement in article 7 letter a and letter c then the holder of the Permit should prohibit Radiation Workers working with radiation to the end of the year.

Article 21 (1) in the event that the worker received a dose of radiation exceeds 100 mSv (one hundred and milisievert) for a period of less than 5 (five) years, then the holder of the permit should be: a. review radiation exposure and to take corrective measures that are necessary;
b. prohibit Radiation Workers working with radiation up to the provision in article 15 letter a are met; and c. make and report a study of the causes of the occurrence of excess Radiation Exposure to BAPETEN.
(2) the study of the causes of the occurrence of excess Radiation Exposure referred to in paragraph (2) Letter c at least include the following: a. a brief description of the incident;
b. reconstruction of contact time and distance with the source by including the assumptions, methods, and/or the calculation of doses received; c. impact posed;

d. determination of the causes of the incident;

e. action already undertaken related to the incident;

f. remedial measures and precautions to prevent recurrence; and g. the conclusion.
Article 22 in the case of workers received Radiation dosage as stipulated in article 19, article 20, and article 21, the holder of the permit is obliged to organize health management workers who get excess radiation exposure as set forth in the regulations of the head of BAPETEN regarding health monitoring.

Article 23


The value of Limit doses to members of the community as referred to in article 2 letter c is assigned to the provisions of: a. the effective Dose of 1 mSv per year (one milisievert);
b. a dose Equivalent to the lens of the eye by 15 mSv (one hundred and fifty milisievert) annually; and c. a dose Equivalent to the skin of 50 mSv (fifty milisievert) per year.

Article 24 (1) the effective Dose as stipulated in article 15 letter a and letter b, letter a, article 16 and article 23 letter a is based on the accumulated dose of acceptance that comes from exposure to Radiation and internal Radiation Exposure Externa.
(2) Effective Dose Determination referred to in subsection (1) must be in accordance with the methodology of calculations as listed in Annex I which is part an integral part of the regulation of the head of BAPETEN.
Article 25 the holder of a permit, to make sure the Dose Limit Value as stipulated in article 15, article 16 and article 23 are not exceeded, it is obligatory: a. the Division of areas of work;

b. monitoring of radiation exposure and/or radioactive contamination in areas of work;

c. monitoring of environmental radioactivity outside the facility or installation; and d. monitoring of Radiation Workers received doses.

Article 26 (1) the holder of the permit, in implementing the Division of work as stipulated in article 25 the letter a should be set: a. the control Area; and/or b. a supervision Area.
(2) the determination of the Division of work as referred to in subsection (1) is adjusted with the utilization of nuclear power.
Article 27 (1) the holder of the permit may specify areas of Control as stipulated in article 26 paragraph (1) letter a on the basis of the criteria of: a. the potential receipt of radiation exposure exceeds 3/8 (tigapersepuluh) Radiation Worker NBD; and/or b. the existence of potential contamination.
(2) the Permit Holder must perform the actions of protection and safety of Radiation required to work in the area of Control referred to in subsection (1).
Article 28 of the radiation protection and Safety Actions are needed to work in the area of Control referred to in article 27 paragraph (2) includes the following: a. the marking and limiting the Control Area set with a clear physical mark or other sign;
b. install or put a warning sign or instructions on the access point and other locations as it deems appropriate in the areas of Control;
c. ensure access Control to the region: 1. only for Radiation Workers; and 2. visitors who enter the Control Area was accompanied by officers of the Radiation Protection; d. providing the equipment monitoring and radiation protective equipment; and/or e. provide the means in the exit area of the control, including: 1. monitoring equipment contamination of skin, and clothed;

2. contamination monitoring equipment against objects or substances that are transferred from the control Area;

3. washing and bathing facilities for decontamination; and/or 4. storage areas for equipment and protective radiation contaminated equipment;

Article 29 (1) the holder of the permit may specify Supervision Areas as stipulated in article 26 paragraph (1) letter b by considering potential receipt of radiation exposure criteria of the individual over society and member of the NBD is less than 3/8 (tigapersepuluh) Radiation Worker NBD, and free of contamination.
(2) the holder of the permit, in the area of supervision of assigned based on considerations as referred to in paragraph (1), shall be: a. mark and limit the Supervision Area designated by signs are clear; and b. put up a sign at the entrance area of Supervision.
Article 30 of the holder of the permit should do a phased radiologik periodically in accordance with the utilization of nuclear power in case there are any indication of the need for changes to the Act: a. the protection and safety of Radiation;

b. limit the control Area; or c. the supervision Area boundaries.

Article 31 (1) the holder of the permit should not be put: a. workers aged less than 18 (sixteen) years, in areas of Control;
b. the radiation Workers in conditions of pregnant women, in the area of work that allows receiving Doses greater than or equal to 1 mSv (one milisievert) per year;
c. Radiation Workers in conditions of women breastfeeding in work areas with the risk of radioactive contamination; and/or d. apprentices for training interns, students, or students who are aged below 16 years in the area of employment.
(2) Radiation Worker women in pregnant conditions referred to in paragraph (1) letter b should report his condition since concerned to know of her pregnancy to the holder of the permit.
Article 32 (1) the holder of the permit should perform monitoring of radiation exposure and/or radioactive contamination in areas of work as stipulated in article 25 the letter b is continuously, periodically, and/or at any time according to the type of –/risk of the utilization of nuclear power.
(2) periodic monitoring Period and during the time referred to in subsection (1) is determined by considering the type of Permit Holders/risk of the utilization of nuclear power.
(3) monitoring of radiation exposure and/or radioactive contamination in areas of work referred to in subsection (1) include the following: a. monitoring radiation exposure Externa;

b. surface contamination; and/or c. air contamination.
Article 33 (1) the holder of the permit should perform monitoring of environmental radioactivity outside the facility or installation referred to in Article 25 of the letter c in accordance with the Environmental management plan (RKL) and Environmental Monitoring Plan (RPL).
(2) monitoring of environmental radioactivity outside the facility or installation referred to in subsection (1) at least includes: a. air;

b. water;

c. land; and d. biota.
(3) the provisions on environmental radioactivity monitoring outside the facility or installation referred to in subsection (1) is set out in the regulations of the head of BAPETEN.
Article 34 (1) the holder of a permit to conduct monitoring of the dose of Radiation Workers received as stipulated in article 25 letter d implemented include radiation exposure Externa and internal radiation exposure.
(2) monitoring of doses administered for radiation exposure Externa as referred to in subsection (1) must be made by the holder of the permit at least: a. one (1) times within 1 (one) month, when using the equipment of individual dose monitoring of types of film badges;
b. one (1) times within 3 (three) months, when using individual dose monitoring equipment type thermoluminisence dosimeter (TLD) badge;
c. one (1) times within 3 (three) months, when using individual dose monitoring equipment type radiophotoluminisence dosimeter badge.
(3) individual dose Monitoring with the use of equipment other than as referred to in paragraph (2) adjusted for the period specified by the manufacturer.
(4) individual dose monitoring Equipment referred to in subsection (2) shall be sent to the laboratory to be evaluated accredited dosimetri.
(5) delivery of individual dose monitoring equipment referred to in subsection (2) must be in accordance with the procedures established by the laboratory dosimetri.
(6) in the event of Radiation Workers potentially receiving internal Radiation Exposure referred to in subsection (1), the holder of the permit should be organized through the measurement of dose monitoring: a. in-vivo with whole body counter; and/or b. in-vitro fertilization bioassay techniques.
(7) the implementation of the monitoring of the dose as referred to in paragraph (6) adapted to the potential acceptance of internal Radiation Exposure.
Article 35 (1) in addition to the dose monitoring as referred to in article 34 paragraph (2), the holder of the permit should perform monitoring of the dose of Radiation Workers against separately at the moment: a. commissioning;
b. testing after installation or facility modifications and changes to operating procedures; c. decommissioning or closure; and/or d. countermeasures against Abnormal Conditions.
(2) dose Monitoring as referred to in paragraph (1) will be conducted to provide data where necessary to make better procedures.
Article 36 (1) the holder of the permit in implementing the provisions of article 25 of the radiation protection equipment provides mandatory (2) Radiation Protection Equipment referred to in subsection (1) include the following: a. the radiation level monitoring equipment and/or radioactive contamination in areas of work;

b. environmental radioactivity monitoring equipment on the outside of the facilities and installations;

c. individual dose monitoring equipment; and/or d. radiation protective equipment.
Article 37 (1) equipment monitoring radiation levels and/or radioactive contamination in areas of work as stipulated in article 36 paragraph (2) letter a include: a. measuring instrument dose or dose rate;

b. measuring instrument of surface contamination; and/or c. gauge air contamination.
(2) the use of monitoring of radiation levels and/or radioactive contamination in areas of work referred to in subsection (1) is adjusted with the utilization of nuclear power.
Article 38 environmental radioactivity monitoring Equipment on the outside of the facilities and installations as referred to in article 36 paragraph (2) letter b is set in the regulations the head of BAPETEN.
Article 39 (1) individual dose monitoring Equipment referred to in Article 36 paragraph (2) Letter c, among others: a. film badge, thermoluminisensi dosimeter (TLD) badge, or a radiofotoluminisensi dosimeter badge; and b. direct reading dosimeter.
(2) the use of individual dose monitoring equipment referred to in subsection (1) is adjusted with the utilization of nuclear power.
Article 40 (1) of radiation Protective Equipment referred to in Article 36 paragraph (2) letter d include among other things: a. the most Radiation Protection clothing less consists of: 1. an apron;

2. lab coat; b. protective equipment respiratory protection;

c. gloves;

d. protective organ; and/or e. glove box.

(2) the use of radiation protective equipment referred to in subsection (1) is adjusted with the utilization of nuclear power.
The fourth part of the Optimization of radiation protection and Safety Article 41 Optimization of radiation protection and Safety as stipulated in article 10 of the letter c must be carried out by the holder of the permit through the determination of: a. Dividing the dose; and/or b. level guide to Medical Exposure.

Article 42 the limiting Dose as referred to in article 41 letter a include Limiting the doses to Radiation Workers: a.; and b. members of the community.

Article 43 (1) Limiting Radiation doses to Workers referred to in Article 42 the letter a is assigned by the holder of the permit with the consent of the head of BAPETEN.
(2) the determination of the limiting Dose as referred to in paragraph (1) was carried out by the holder of the permit on: a. the construction phase for new installations or facilities; and/or b. stage of operation, and decommissioning or closure for the facility or installation that is already operating when the regulations apply BAPETEN's head.
(3) the holder of a permit, to get the approval of the head of BAPETEN regarding determination of the limiting Dose as referred to in paragraph (1), the calculation should convey the determination of the limiting Radiation doses to Workers.
(4) determination of the limiting Dose as referred to in subsection (1) is part of the document radiation safety and protection programs.
(5) in the case of radiation Workers work more than one facilities, Limiting the dose should be set taking into account the contribution to Dose from each facility or installation.
Article 44 (1) the holder of a permit must carry out a phased against Limiting Radiation doses to Workers referred to in Article 43 paragraph (1) for the operation of the facility or installation.
(2) if the results of phased as referred to in subsection (1) shows he had to do changes to the limiting Radiation doses to Workers, Permit Holders can apply changes to the head of BAPETEN.
(3) the filing of a change of Border Radiation doses to Workers apply the provisions referred to in Article 43.
Article 45 (1) dose of Radiation Workers in the event of exceeding the limiting Dose but does not exceed the Limit values of the Permit Holder, the Dose should be: a. review the execution of the surgical procedure; and b. review the analysis of the limiting Dose selection in accordance with the provisions referred to in Article 44;
(2) In terms of the results of the evaluation as referred to in paragraph (1) letter a and b require changes Limiting the dose, the holder of a permit must submit the change to the head of BAPETEN Dose Limiting.
Article 46 (1) Limiting the doses to members of the community as referred to in article 42 the letter b is assigned does not exceed 0.3 mSv (three tenths miliSievert) per year.
(2) the value of the limiting dose as referred to in subsection (1) is in effect for one (1) area.
(3) in case there is more than one (1) facilities in one area as referred to in paragraph (2) the compulsory Dose Limiting set taking into account the contribution of the dosage of each facility or installation.
Article 47 (1) the level of Exposure for Medical guidelines as referred to in article 41 the letter b reserved only for Medical Exposure in diagnostic radiology and nuclear medicine, and intervensional.
(2) further Provisions concerning Medical Exposure Guide to level as referred to in paragraph (1) in accordance with the type of utilization of nuclear power is regulated in the regulations the head of BAPETEN.
CHAPTER IV SAFETY and RADIATION PROTECTION PROGRAMS Section I General Article 48 (1) the holder of the permit in implementing safety and Radiation Protection as stipulated in article 10 to with article 47 should devise, implement, and develop safety and radiation protection programs.
(2) preparation of safety and radiation protection programs as intended in paragraph (1) shall be based on: a. evaluation of radiologik; and b. the study of salvation.
The second part of the evaluation of the safety Studies and Radiologik Article 49 (1) evaluation of radiologik as stipulated in article 48 paragraph (2) letter a is adjusted with the magnitude of the Normal Exposure and probability of potential Exposure.
(2) evaluation of radiologik referred to in subsection (1) at least include the following: a. the identification of the sources of exposure to Normal and the probability of Potential Exposure;

b. an estimate of the magnitude and likelihood of doses received; and c. the identification of the actions necessary to meet the protection principle of optimization.
Article 50 the Safety Review referred to in Article 48 paragraph (2) letter b at least include the following: a. the nature of, and the possibility of Potential Exposure;

b. restrictions and technical conditions for the operation of the source;
c. probability of failure of structures, systems, components that are related to the protection and safety of Radiation which leads to the occurrence of Potential Exposure and the consequences in case of failure;
d. possible errors operating procedures related to the protection and the safety and consequences if an error occurs; e. changes in the environment that affect the hue of protection and safety of Radiation; and f. the impact it does modify the Resource Protection and safety against radiation.

Article 51 scope of implementation evaluation radiologik as stipulated in article 49 and safety review referred to in article 50 adapted to the type of utilization of nuclear energy.

The third section of the program description the radiation safety and protection of article 52 (1) safety and radiation protection programs as stipulated in article 48 paragraph (1) at least include the following: a. the radiation safety of the organizers, which include the determination of the responsibility of the organizers of the Radiation Safety;
b. personnel working in the facility or installation of programs include education and training concerning Radiation safety and Protection; c. Radiation Protection equipment;

d. the determination of the Division of work;

e. monitoring of radiation exposure and/or radioactive contamination in areas of work;

f. monitoring environmental radioactivity outside the facility or installation;
g. program quality assurance of radiation safety and Protection which contains among other things the procedure of phased implementation and audit of safety and radiation protection programs on a regular basis;
h. emergency response plans in case of a situation that requires intervention; i. determination of the limiting Dose; and j. procedures include operating procedures according to the type of the source used in the utilization of nuclear power, the Division of areas of work Permit holders are assigned, health monitoring, monitoring of radiation Workers received Doses, and recording and reporting.
(2) the scope and contents of safety and radiation protection programs tailored to the utilization of nuclear power.
(3) Systematic safety and radiation protection programs in General is contained in annex II that is part inseparable in the regulations the head of BAPETEN.
Article 53 (1) the recording referred to in Article 52 paragraph (1) Letter j include: a. the results of monitoring of radiation levels and/or work in the area of contamination;

b. environmental radioactivity monitoring results outside of the facilities and installations;

c. the results of monitoring of Radiation Workers received doses; and d. the results of health monitoring for Radiation Workers.
(2) the Record referred to in subsection (1) shall be made and kept by the holder of the permit.
(3) the recording referred to in paragraph (1) letter a and b mandatory Permit Holder stored by at least 5 (five) years.
(4) the Record referred to in subsection (1) of the letters c and d compulsory kept by the holder of the permit at least 30 (thirty) years counted since Radiation Workers quit his job.
(5) the Record referred to in subsection (1) must be presented by the holder of the permit at the time of the inspection conducted by BAPETEN.
Article 54 (1) the report referred to in Article 52 paragraph (1) Letter j include: a. the results of monitoring of radiation levels and/or work in the area of contamination;

b. environmental radioactivity monitoring results outside of the facilities and installations;

c. the results of monitoring of Radiation Workers received doses; and d. the results of health monitoring for Radiation Workers.
(2) the report referred to in subsection (1) must be submitted by the holder of the permit in writing to the head of BAPETEN longest sixty (60) business days counted since the monitoring referred to in paragraph (1) was carried out in accordance with the Sources used in the utilization of nuclear power.
Article 55 further Provisions regarding health monitoring for Radiation Workers as stipulated in article 52 paragraph (1) Letter j, program quality assurance as referred to in article 52 paragraph (1) the letter g and the emergency response plan referred to in Article 52 paragraph (1) the letter h, regulated in the regulations the head of BAPETEN.

Chapter V TRANSITIONAL PROVISION Article 56 (1) provisions on Radiation Worker Dose Limit Value for the lens of the eye as stipulated in article 15 of the letters c obligatory are met by the holder of the permit is the longest of three (3) years commencing from the date of entry into force of the regulation the head of BAPETEN.
(2) the worker's Radiation Dose Limit Value for the lens of the eye within the period referred to in subsection (1) is 150 mSv (one hundred and fifty milisievert).
CHAPTER VI CLOSING PROVISIONS Article 57 of the regulation at the time the head of BAPETEN this took effect, the decision of the head of the nuclear power Watchdog Agency number 01/Ka-BAPETEN/V-Safety Provisions of 99 Against Radiation was revoked and declared inapplicable.

Article 58 Regulations head of BAPETEN this took effect upon promulgation.

In order to make everyone aware of it, ordered the enactment of regulations this with his head of BAPETEN in Republic Indonesia.

Established in Jakarta on March 13, 2013, HEAD of the REPUBLIC'S NUCLEAR POWER WATCHDOG AGENCY, the US NATIO LASMAN Enacted in Jakarta on May 6, 2013


MINISTER of LAW and HUMAN RIGHTS REPUBLIC of INDONESIA, AMIR SYAMSUDDIN Attachment: bn672-2013 fnFooter ();