SSMFS 2008:23
Swedish Radiation Safety Authority
Regulatory Code
ISSN: 2000-0987
The Swedish Radiation Safety Authority’s Regulations on Protection of Human Health and the Environment in connection with Discharges of Radioactive Substances from certain Nuclear Facilities
Please note that translated versions of the Authority’s regulations lack legal force and are for information purposes only.
Swedish Radiation Safety Authority
Regulatory Code
ISSN 2000-0987 Publisher: Ulf Yngvesson
The Swedish Radiation Safety Authority's
Regulations on Protection of Human Health
Published on 30 January 2009
and the Environment in connection with
Discharges of Radioactive Substances from
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certain Nuclear Facilities;
issued on 19 December 2008.
On the basis of Section 7 of the Radiation Protection Ordinance 2 (1988:293), the Swedish Radiation Safety Authority hereby issues the following regulations.
Application and definitions
Section 1 These regulations apply to the following nuclear facilities for which the Government has granted licences under the Nuclear Activities Act (1984:3): 1. nuclear power reactors, 2. reactors for research or materials testing, 3. plants for manufacturing of uranium pellets and nuclear fuel bundles, 4. facilities for storage or other handling of used nuclear fuel, and 5. facilities for storage, treatment or final disposal of nuclear substances or nuclear waste. The regulations apply to all discharges of radioactive substances from nuclear facilities that are directly related to normal operating conditions at the respective facility. The regulations do not apply to: 1. shallow land burial of low activity nuclear waste under Section 16 of the Ordinance on Nuclear Activities (1984:14), nor 2. transports of nuclear substances or nuclear waste outside the operating area of a facility, nor 3. dismantling of nuclear facilities, nor 4. the conditions following sealing of a waste facility referred to by the Swedish Radiation Safety Authority's Regulations (SSMFS 2008:37) on the protection of human health and the environment in connection with the final management of spent nuclear fuel and nuclear waste.
1 These regulations were issued previously in the Swedish Radiation Protection Authority's Regulatory Code (SSI FS 2000:12). 2 Cf. Council Directive 96/29/Euratom of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation. OJ L159, 29/06/1996, p. 1 (Celex 31996L0029). 1
Definitions Rules of consideration and protection of human
Section 2 In these regulations the following terms and concepts are used health and the environment
with the meanings specified here. Section 3 Human health and the environment shall be protected from the best available technique: the use of the most effective method to limit harmful effects of ionising radiation while a nuclear facility is in operathe discharge of radioactive substances and tion as well as in the future. their harmful effects on human health and the Discharges of radioactive substances must not cause more severe efenvironment, and which does not give rise to fects on human health and the environment outside the borders of Sweden unreasonable costs than levels accepted within Sweden.
effective dose: the sum of all equivalent doses to organs and Section 4 The limitation of discharges of radioactive substances from tissues, weighted by their various sensitivity to nuclear facilities shall be based upon optimisation of radiation protection radiation while using the best available technique. Such optimisation of radiation committed effective dose: the total effective dose after an intake of radioprotection shall include all facilities located within the same geographical active substances, calculated over 50 years (for area. children, 70 years) The possibility that the limitation of discharges to the environment reference group: a representative real or hypothetical group may imply that radiation doses to the personnel will be increased shall be from the general public that could be expected taken into account during such optimisation, as well as the consequences to receive the largest radiation doses from a of other waste management. source
environmental surveil- discharge surveillance and environment checks Section 5 The effective dose to any individual in the reference group by a lance: yearly discharge of radioactive substances to water and air from all facilities situated within the same geographical area shall not exceed 0.1 milgoal value: the lowest level of discharges of radioactive lisievert (mSv). The effective dose, by which is meant the dose from exsubstances from a nuclear power reactor that ternal exposure and the committed dose from internal exposure, shall be could be achieved within a specified period of integrated over a period of 50 years. time When calculating doses to individuals in the reference group, children normal operating condi- management within given conditions and limias well as adults shall be taken into account. Dose factors to be used for tions: tations according to the respective Operational oral intake as well as intake by inhalation are given in annex III of the Limits and Conditions ('STF') for a facility Directive 96/29/Euratom. environment check: collecting samples and measuring radioactive If the estimated dose is 0.01 mSv or higher per calendar year, realistic substances within the vicinity of a nuclear calculations shall be performed regarding the most affected area. The facility calculations shall be based upon measured dispersion data and knowledge
optimisation of radiation limitation of radiation doses to humans as far of the circumstances in the most affected area during the time period protection: as reasonably achievable while taking finan- concerned. cial and societal factors into account The underlying documentation for dose estimations made and the reference value: the level of discharges that is representative at methods used to assess the relationship between the discharged activity optimal management with full function of and the effective dose shall be submitted to the Swedish Radiation Safety systems of significance for the generation and Authority for review.
limitation of discharges from a nuclear power reactor Section 6 Reference values shall be determined for each nuclear power reactor regarding the yearly discharge of separate radioactive substances discharge surveillance: collecting samples and measuring discharges or groups of radioactive substances. The reference values shall be deterof radioactive substances to water and air mined by the licence holders and be reported to the Swedish Radiation Safety Authority for review. The underlying documentation for the suggested reference values shall be enclosed.
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Rules of consideration and protection of human
health and the environment
Section 3 Human health and the environment shall be protected from the harmful effects of ionising radiation while a nuclear facility is in operation as well as in the future. Discharges of radioactive substances must not cause more severe effects on human health and the environment outside the borders of Sweden than levels accepted within Sweden.
Section 4 The limitation of discharges of radioactive substances from nuclear facilities shall be based upon optimisation of radiation protection while using the best available technique. Such optimisation of radiation protection shall include all facilities located within the same geographical area. The possibility that the limitation of discharges to the environment may imply that radiation doses to the personnel will be increased shall be taken into account during such optimisation, as well as the consequences of other waste management.
Section 5 The effective dose to any individual in the reference group by a yearly discharge of radioactive substances to water and air from all facilities situated within the same geographical area shall not exceed 0.1 millisievert (mSv). The effective dose, by which is meant the dose from external exposure and the committed dose from internal exposure, shall be integrated over a period of 50 years. When calculating doses to individuals in the reference group, children as well as adults shall be taken into account. Dose factors to be used for oral intake as well as intake by inhalation are given in annex III of the Directive 96/29/Euratom. If the estimated dose is 0.01 mSv or higher per calendar year, realistic calculations shall be performed regarding the most affected area. The calculations shall be based upon measured dispersion data and knowledge of the circumstances in the most affected area during the time period concerned. The underlying documentation for dose estimations made and the methods used to assess the relationship between the discharged activity and the effective dose shall be submitted to the Swedish Radiation Safety Authority for review.
Section 6 Reference values shall be determined for each nuclear power reactor regarding the yearly discharge of separate radioactive substances or groups of radioactive substances. The reference values shall be determined by the licence holders and be reported to the Swedish Radiation Safety Authority for review. The underlying documentation for the suggested reference values shall be enclosed. 3
Goal values shall be determined for each nuclear power reactor regarding the discharge of separate radioactive substances or groups of radioactive substances showing which levels the discharges could be reduced to in a specified period of time.
General provisions
Section 7 Environmental surveillance shall be performed at nuclear facilities.
Section 8 The environmental surveillance shall be subject to quality assurance and shall be documented according to the principles of the ISO 9000 family. The measuring laboratories used in the environmental surveillance shall take part in intercomparison (intercalibration) on request by the Swedish Radiation Safety Authority.
Section 9 Nuclear power reactors shall have action plans to limit the discharge of radioactive substances in the event of fuel damage. The plans shall describe the strategy to prevent fuel damage as well as the measures to be taken in order to limit discharges of radioactive substances to the environment should fuel damage occur.
Section 10 In the event of discharge of radioactive substances to air or water implying that the dose, under Section 5, to any individual in the reference group will exceed 0.01 mSv per month, or if the results from environment surveillance show abnormal levels of radioactive substances, the Swedish Radiation Safety Authority shall be informed as soon as possible.
Section 11 Before new facilities are commissioned or a practice is otherwise changed to imply new paths or sources of discharge, or so that a preexisting path of discharge is affected, investigations shall be conducted in order to map the extent of the new discharges and their composition, their dispersion in the environment and dispersion factor and expected doses. The investigations shall be submitted to the Swedish Radiation Safety Authority for review.
Discharge surveillance
Section 12 Discharges of radioactive substances from a nuclear facility into air and water shall be checked by means of measurements. The detection levels of the instruments shall be chosen to afford comparison with the values stated in Section 5 and determined under Section 6, respectively.
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Section 13 Releases into air via the main stack of a nuclear power reactor shall be checked by means of continuous nuclide-specific measurements of volatile radioactive substances such as inert gasses, nuclide-specific measurements of continuously collected samples of iodine and particlebound radioactive substances, and measurements of carbon-14 and tritium. Releases into air from reactors for research or materials testing shall be checked by means of nuclide-specific measurements of volatile radioactive substances such as inert gasses and by means of nuclide-specific measurements of continuously collected samples of iodine and particlebound radioactive substances. Releases into air from plants for manufacturing of uranium pellets and nuclear fuel bundles, for storage or other handling of spent nuclear fuel, or for the storage, treatment or final disposal of nuclear substances or nuclear waste shall be checked by means of nuclide-specific measurements of continuously collected samples of particle-bound radioactive substances and, when applicable, of iodine and tritium.
Section 14 Discharges into water shall be checked by means of measurements of representative samples for each path of discharge. The analyses shall include nuclide-specific measurements of gamma- and alphaemitting radioactive substances and, when applicable, of strontium-90 and tritium.
Section 15 Representative monthly samples of discharges into water from nuclear power reactors, and reactors for research or materials testing shall be sent to the Swedish Radiation Safety Authority within two months after the end of the month concerned. Representative yearly samples of discharges into water from nuclear power reactors and reactors for research or materials testing shall be sent to the Swedish Radiation Safety Authority within three months after the end of the year concerned.
Section 16 The function of the monitoring equipment and systems to limit discharges shall be checked regularly and whenever a malfunction is suspected. Written instructions for the maintenance of the equipment shall be available. Changes to the regular system for measuring discharges shall be approved in advance by the Swedish Radiation Safety Authority.
Section 17 The monitoring equipment for releases to air may, without the special permission of the Swedish Radiation Safety Authority, be out of operation for a maximum period of 24 hours for maintenance of the systems for sampling and monitoring, or in the event of a malfunction. If the monitoring equipment needs to be out of operation for a longer period of time, the operation of the facility may continue during nonoffice hours until such time that the Swedish Radiation Safety Authority has been informed, provided that the operating conditions are judged to be 5
stable in the event of discharges. The reasons for such judgment shall be demonstrated when the Swedish Radiation Safety Authority is informed. When the regular monitoring system is out of operation, monitoring of discharges shall be carried out sufficiently by other means to determine the levels of discharges. Other shutdown of the monitoring system may only be made following special permission granted by the Swedish Radiation Safety Authority.
Section 18 The reactor water at nuclear power reactors shall be analysed. The analyses shall include nuclide-specific measurements of gamma- and alpha-emitting radioactive substances as well as strontium-90 and tritium.
Section 19 If diffuse leakage of radioactive substances is suspected, and such leakage is not measurable, an investigation shall be conducted in order to determine an upper limit for the possible and non-detectable discharge from the facility into air and water.
Environment checks
Section 20 Environment checks shall be conducted in the vicinity of a nuclear facility according to a schem e determined by the Swedish Radiation Safety Authority. In such scheme, rules for sampling, treatment, analysis, evaluation and reporting, as well as the kind of samples and the sites for sampling are specified.
Section 21 In connection with any event that has brought about increased discharge of radioactive substances into the environment, a separate environment check shall be conducted if requested by the Swedish Radiation Safety Authority. If so, the consequences for the affected area shall be judged.
Section 22 Monitoring of gamma radiation shall be performed continuously in the vicinity of nuclear power reactors and reactors for research or materials testing. Monitoring shall be carried out within each 30-degree sector on land at about 1 kilometre from the reactor.
Section 23 Continual registration of meteorological conditions shall be made at nuclear power reactors and reactors for research or materials testing.
Reporting
Section 24 The licence holders shall, on the part of nuclear power reactors, report to the Swedish Radiation Safety Authority not later than 31 January every year on the measures that have been taken or are planned to 6 be taken in order to limit the discharge of radioactive substances with a
stable in the event of discharges. The reasons for such judgment shall be view to reaching the goal values under Section 6. If the reference values demonstrated when the Swedish Radiation Safety Authority is informed. are exceeded, the measures planned with a view to reaching the reference When the regular monitoring system is out of operation, monitoring values shall be reported. of discharges shall be carried out sufficiently by other means to determine the levels of discharges. Section 25 The discharge of radioactive substances into air and water Other shutdown of the monitoring system may only be made follow- under Sections 12-14, shown as discharge of activity, and doses to indiing special permission granted by the Swedish Radiation Safety Authori- viduals in /the reference group under Section 5, shall be reported to the ty. Swedish Radiation Safety Authority in accordance with Appendix 1.
Section 18 The reactor water at nuclear power reactors shall be analysed. Section 26 If deviations from Sections 12-14 have occurred, or if moni- The analyses shall include nuclide-specific measurements of gamma- and toring has been carried out in accordance with Section 17, third paraalpha-emitting radioactive substances as well as strontium-90 and tritium. graph, information about the monitoring systems used during the period covered as well as the monitoring method and the frequency of such mon- Section 19 If diffuse leakage of radioactive substances is suspected, and itoring shall be included in reports regarding discharges. such leakage is not measurable, an investigation shall be conducted in order to determine an upper limit for the possible and non-detectable Section 27 The results of environment checks shall be reported to the discharge from the facility into air and water. Swedish Radiation Safety Authority in accordance with Appendix 2.
Section 28
Environment checks
Events leading to increased discharge of radioactive substances from nuclear facilities shall be reported as soon as possible to the Swe- Section 20 Environment checks shall be conducted in the vicinity of a dish Radiation Safety Authority, including information on measures taken nuclear facility according to a schem e determined by the Swedish Radiato limit such discharge. tion Safety Authority. In such scheme, rules for sampling, treatment, analysis, evaluation and reporting, as well as the kind of samples and the sites for sampling Exemptions
are specified. Section 29 If there are particular grounds, the Swedish Radiation Safety Authority may grant exemptions from these regulations if this can be Section 21 In connection with any event that has brought about increased done without circumventing the aim of the regulations. discharge of radioactive substances into the environment, a separate environment check shall be conducted if requested by the Swedish Radiation These regulations enter into force on 1 February 2009. Safety Authority. If so, the consequences for the affected area shall be judged. SWEDISH RADIATION SAFETY AUTHORITY Section 22 Monitoring of gamma radiation shall be performed continuously in the vicinity of nuclear power reactors and reactors for research or materials testing. Monitoring shall be carried out within each 30-degree sector on land at about 1 kilometre from the reactor. ANN-LOUISE EKSBORG
Section 23 Continual registration of meteorological conditions shall be Ann-Christin Hägg made at nuclear power reactors and reactors for research or materials testing.
Reporting
Section 24 The licence holders shall, on the part of nuclear power reactors, report to the Swedish Radiation Safety Authority not later than 31 January every year on the measures that have been taken or are planned to 6 be taken in order to limit the discharge of radioactive substances with a 7
Appendix 1
Reporting to the Swedish Radiation Safety Authority
1. For nuclear power reactors and, if applicable, for reactors for research or materials testing, measurements of releases/discharges into: air of inert gasses, iodine, carbon-14, tritium and particle-bound radioactive substances, water of tritium and gamma-emitting radioactive substances, and air and water of strontium-90 and alpha-emitting radioactive substances shall be reported every half year, within three months after the end of the half year covered by the report. The results shall be summed up monthly.
2. For plants for manufacturing of uranium pellets and nuclear fuel bundles, facilities for storage or other handling of spent nuclear fuel, and facilities for storage, treatment or final disposal of nuclear substances or nuclear waste, measurements of releases/discharges into: air of particle-bound radioactive substances and, if appropriate, iodine, water of gamma-emitting radioactive substances, and air and water of alpha-emitting radioactive substances and, if applicable, strontium-90 and tritium shall be reported every half year and within three months after the end of the half year covered by the report. The results shall be summed up monthly.
3. A report covering the second half year shall at the same time form the yearly report and summarise: all discharges to air and water from nuclear facilities during the year, the dose to representative individuals from reference groups, diffuse discharges, the uncertainty factors of the measurements and the levels of detection, and the methods selected for measurements performed. The report shall be submitted within three months after the end of the calendar year covered by the report. Radioactive substances in the reactor water at nuclear power reactors shall be reported to the Swedish Radiation Safety Authority on request.
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Appendix 1 Appendix 2
Environment checks
Reporting to the Swedish Radiation Safety Authority The results of environment checks shall, when applicable, be reported to 1. For nuclear power reactors and, if applicable, for reactors for research the Swedish Radiation Safety Authority in accordance with the table beor materials testing, measurements of releases/discharges into: low. air of inert gasses, iodine, carbon-14, tritium and particle-bound radioactive substances, Kind of check Reporting water of tritium and gamma-emitting radioactive substances, and measurements of samples of Every half year and within three air and water of strontium-90 and alpha-emitting radioactive substances plants, milk, water and sediment: months after the end of the half year shall be reported every half year, within three months after the end of the covered by the report; the results of half year covered by the report. The results shall be summed up monthly. measurements shall, when applicable, be summed up per month or per 2. For plants for manufacturing of uranium pellets and nuclear fuel bunquarter of a year depending on when dles, facilities for storage or other handling of spent nuclear fuel, and the sample was taken facilities for storage, treatment or final disposal of nuclear substances or nuclear waste, measurements of releases/discharges into: sampling in spring and intense Not later than 30 September in the air of particle-bound radioactive substances and, if appropriate, iodine, sampling: same year water of gamma-emitting radioactive substances, and air and water of alpha-emitting radioactive substances and, if applicable, sampling in autumn: Not later than 31 March the followstrontium-90 and tritium shall be reported every half year and within three ing year months after the end of the half year covered by the report. The results shall be summed up monthly. particular investigation under Within one month after the last sam- Section 21: ple taken or as determined by the 3. A report covering the second half year shall at the same time form the Swedish Radiation Safety Authority yearly report and summarise: all discharges to air and water from nuclear facilities during the year, monitoring of gamma radiation Every half year and within three the dose to representative individuals from reference groups, under Section 22: months after the end of the half year diffuse discharges, covered by the report; the results of the uncertainty factors of the measurements and the levels of detec- monitoring shall be summarised per tion, and quarter of a year the methods selected for measurements performed. The report shall be submitted within three months after the end of the meteorological conditions: To the extent determined by the calendar year covered by the report. Swedish Radiation Safety Authority Radioactive substances in the reactor water at nuclear power reactors shall be reported to the Swedish Radiation Safety Authority on request. A report covering the second half year shall at the same time form the yearly report and summarise: the measurements performed during the year, major deviations from the surveillance programme, uncertainty factors of measurements and the levels of detection, and the methods selected for measurements performed. The report shall be submitted within three months after the end of the calendar year covered by the report.