fs: ssmfs

publisher: Strålsäkerhetsmyndigheten

title: Strålsäkerhetsmyndighetens allmänna råd om begränsning av allmänhetens exponering för 1 elektromagnetiska fält

text: 1. Tillämpningsområde

type: stycke

text: 1.1 Syftet med dessa allmänna råd är att skydda individer ur allmänheten från akuta skadliga biologiska effekter vid exponering för elektromagnetiska fält i frekvensområdet 0 Hz - 300 GHz. De allmänna råden bygger på rekommendationer från Europeiska unionens råd . Råden avses vara vägledande vid tillämpningen av

text: 6 § strålskyddslagen (1988:220)

text: 1.2 I de allmänna råden ges grundläggande begränsningar samt referensvärden. De grundläggande begränsningarna säkerställer att elektriska eller magnetiska fenomen som kan uppträda i kroppen inte stör funktioner i nervsystemet eller ger upphov till skadlig värmeutveckling. Referensvärdena utgörs av storheter som är mätbara utanför människokroppen. De är härledda ur de grundläggande begränsningarna och säkerställer att de grundläggande begränsningarna inte överskrids. Om uppmätta värden överstiger referensvärdena, innebär detta inte nödvändigtvis att de grundläggande begränsningarna överskrids. I sådana fall gäller enligt dessa allmänna råd de grundläggande begränsningarna. De grundläggande begränsningarna är, enligt internationella rekommendationer, satta vid ungefär två procent av de nivåer vid vilka akuta biologiska effekter är vetenskapligt säkerställda.

text: 1 Dessa allmänna råd har tidigare kungjorts i Statens strålskyddsinstituts författningssamling (SSI FS 2002:3). Jfr

text: rådets rekommendation 1999/519/EG av den 12 juli 1999

text: om begränsning av allmänhetens exponering för elektromagnetiska fält (0 Hz - 300 GHz), (EGT L 199, 30.7.1999, s. 59, Celex 399L0519). 1

text: 1.3 Dessa allmänna råd omfattar områden där allmänheten kan vistas under sådana tider att begränsningarna är av betydelse.

text: 1.4 Referensvärdena garanterar inte att medicinteknisk utrustning såsom proteser av metall, pacemaker eller andra implantat inte påverkas eller drabbas av funktionsstörningar. Sådana frågor behandlas i bestämmelser om elektromagnetisk kompatibilitet och medicintekniska produkter.

text: 1.5 Dessa allmänna råd tillämpas inte på arbetstagare som i sin yrkesverksamhet exponeras för elektromagnetiska fält. För exponering av sådana arbetstagare gäller föreskrifter från Arbetsmiljöverket.

text: 2. Grundläggande begränsningar

text: 2.1 Fält som är sådana att de grundläggande begränsningarna enligt tabell

type: rubrik

text: 1 överskrids, bör inte förekomma i något område där allmänheten vistas enligt punkt 1.3.

text: Tabell 1 Grundläggande begränsningar för elektriska, magnetiska och elektromagnetiska fält (0 Hz - 300 GHz)

text: s t p l) e p ) t de) ro th er tä k e lk de) h bå är e et s s thet th v är it g ti v oc e tä tä ti lv d in n m l SAR u l SAR em ln g ek de a a tr des ff e k k x Frekvensområde ö o o Ma fl Strö (e SAR (h m L (huv L (E Strå S 2 2 (mT) (mA/m ) (W/kg) (W/kg) (W/kg) (W/m )

text: 0 Hz 40 - - - - - > 0 Hz - 1 Hz - 8 - - - - 1 Hz - 4 Hz - 8/f - - - - 4 Hz - 1 kHz - 2 - - - - 1kHz - 100 kHz - f/500 - - - -

text: 100 kHz - 10 MHz - f/500 0,08 2 4 - 10 MHz - 10 GHz - - 0,08 2 4 - 10 GHz - 300 GHz - - - - - 10

text: f är frekvensen uttryckt i Hz. Strömtäthet beräknas som medelvärdet över en area om 1 cm vinkelrätt mot strömmens riktning. Samtliga SAR-värden (specific absorption rate) avser medelvärdet under en sexminutersperiod. Lokal SAR beräknas som medelvärdet över en massa om 10 g sammanhängande vävnad.

text: 3. Referensvärden

text: 3.1 Referensvärden är mätbara storheter som är härledda ur de grundläggande begränsningarna. Dessa anges i tabell 2. Värdena bör inte överskridas i något område där allmänheten vistas enligt punkt 1.3.

text: 3.2 Referensvärdena enligt tabell 2 säkerställer att de grundläggande begränsningarna i tabell 1 inte överskrids.

text: Tabell 2 Referensvärden för allmänhetens exponering för elektromagnetiska fält (0 Hz – 300 GHz)

text: Elektrisk Magnetisk Magnetisk Ekvivalent fältstyrka (E) fältstyrka flödestäthet strålningstäthet Frekvensområde (H) (B) för en plan våg (V/m) (A/m) (PT) Seq (W/m )

text: 4 4 0 Hz - 1 Hz - 3,210 410 - 4 2 4 2 > 1 Hz - 8 Hz 10000 3,210 /f 410 /f - 8 Hz - 25 Hz 10000 4000/f 5000/f - 5 25 Hz - 800 Hz 2,510 /f 4000/f 5000/f - 5 800 Hz – 3 kHz 2,510 /f 5 6,25 -

text: 3 kHz - 150 kHz 87 5 6,25 - 5 5 150 kHz - 1 MHz 87 7,310 /f 9,210 /f - 4 1/2 5 5 1 MHz - 10 MHz 8,710 /f 7,310 /f 9,210 /f - 10 MHz - 400 MHz* 28 0,073 0,092 2 1/2 1/2 1/2 1,375 f 0,0037 f 0,0046 f 8 400 MHz - 2 GHz f/(210 ) 1000 1000 1000

text: 2 GHz - 300 GHz 61 0,16 0,20 10

text: * I området 10 MHz - 110 MHz gäller dessutom 45 mA som referensvärde för inducerad ström i varje extremitet.

text: f är frekvensen uttryckt i Hz.

text: 2 2 2

text: Vid frekvenser mellan 100 kHz och 10 GHz beräknas Seq, E , H och B som medelvärden över en sexminutersperiod.

text: 2 2 2

text: Vid frekvenser större än 10 GHz beräknas Seq, E , H och B som medelvärden över

text: -9 1,05

text: en period om 68/(f  10 ) minuter, där f uttrycks i Hz.

text: Medelvärdet för E-, H- och B-fält beräknas som kvadratroten ur medelvärdet under angiven tid av respektive fälts kvadrater.

text: 4. Exponering för pulser och kortvarig exponering

text: 4.1 För pulser med varaktigheten tp, bör, för de grundläggande begränsningarna och referensvärdena, frekvensen f = 0,5/tp användas. 4.2 Vid exponering av huvudet för pulsmodulerade signaler i frekvensområdet 0,3 GHz - 10 GHz, med pulslängd mindre än 30 mikrosekunder, bör ytterligare en grundläggande begränsning införas, så att den absorberade energin per puls inte överstiger 2 millijoule per kilogram räknat som medelvärdet över 10 gram sammanhängande vävnad. 4.3 För toppvärden avseende E- , H- respektive B-fält bör de effektivvärden som visas i tabell 2 multiplicerade med en faktor enligt tabell 3 tilllämpas.

text: Tabell 3 Faktorer för beräkning av toppvärden

text: Frekvensområde Faktor < 100 kHz 2 D 5 100 KHz – 10 MHz 10 där D = (0,665·log (f/10 ) + 0,176) * 10 MHz – 300 GHz 32

text: * f uttrycks i Hz

text: 5. Samtidig exponering för olika frekvenser

text: Vid samtidig exponering för fält med olika frekvenser bör hänsyn tas till att fälten kan adderas till att ge en biologisk effekt av visst slag. Därvid görs separata bedömningar som avser nervretningar respektive termiska effekter i kroppen.

text: Grundläggande begränsningar

text: 5.1 Vid elektriska retningar med frekvenser mellan 1 Hz och 10 MHz summeras den inducerade strömtätheten enligt ekvationen: 10 MHz Ji 6 d 1  i = 1 Hz JLi

text: 5.2 Vid termisk påverkan med frekvenser över 100 kHz summeras SARvärden och strålningstäthet enligt ekvationen: 10 GHz 300 GHz SARi Si  +  d 1

text: 6 6

text: i = 100 kHz SARL i > 10 GHz SL

text: där Ji är strömtätheten vid frekvensen i, JLi är begränsningen enligt tabell 1 för strömtäthet vid frekvensen i, SARi är det SAR-värde som ges av exponeringen vid frekvensen i, SARL är begränsningen enligt tabell 1 för SAR, Si är strålningstätheten vid frekvensen i och 4 SL är begränsningen enligt tabell 1 för strålningstäthet.

text: Referensvärden

text: 5.3 För att undvika elektrisk retning vid frekvenser upp till 10 MHz bör följande två ekvationer tillämpas: 1 MHz 10 MHz

text: Ei Ei

text: 6  + 6  d 1

text: i = 1 Hz ELi i > 1 MHz a

text: och

text: 150 kHz 10 MHz

text: Hk Hk

text: 6  + 6  d 1

text: k = 1 Hz HLk k > 150 kHz b

text: där Ei är elektrisk fältstyrka vid frekvensen i, ELi är referensvärdet enligt tabell 2 för elektrisk fältstyrka vid frekvensen i, Hk är magnetisk fältstyrka vid frekvensen k, HLk är referensvärdet enligt tabell 2 för magnetisk fältstyrka vid frekvensen k, a = 87 V/m och b = 5 A/m.

text: 5.4 För att undvika termiska effekter vid frekvenser över 100 kHz bör följande två ekvationer tillämpas: 1 MHz 2 300 GHz 2

text: Ei Ei  +  d 1

text: 6 2 6 2

text: i = 100 kHz c i > 1 MHz ELi

text: och

text: 150 kHz 2 300 GHz 2

text: Hk Hk  +  d 1

text: 6 6

text: 2 2 k = 100 kHz d k > 150 kHz HLk

text: där Ei är elektrisk fältstyrka vid frekvensen i, ELi är referensvärdet enligt tabell 2 för elektrisk fältstyrka vid frekvensen i, Hk är magnetisk fältstyrka vid frekvensen k, HLk är referensvärdet enligt tabell 2 för magnetisk fältstyrka vid frekvensen k, 4 1/2 c = 8,7  10 / f V/m och d = 7,3  10 / f A/m. I båda fallen uttrycks f i Hz.

text: STRÅLSÄKERHETSMYNDIGHETEN

text: ANN-LOUISE EKSBORG

text: Jimmy Estenberg 5

type: foreskrift


text: Swedish Radiation Safety Authority Regulatory Code

text: ISSN 2000-0987

text: The Swedish Radiation Safety Authority’s regulations and general advice concerning safety in connection with the disposal of nuclear material and nuclear waste

text: Please note that translated versions of the Authority’s regulations lack legal force and are for information purposes only.

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: The Swedish Radiation Safety Authority’s regulations

text: Published on

text: concerning safety in connection with the disposal of

text: 30 January 2009

text: nuclear material and nuclear waste;

text: issued on 19 December 2008.

text: On the basis of Sections 20a and 21 of the Nuclear Activities Ordinance (

text: ), the Swedish Radiation Safety Authority hereby issues the following regulations.

text: Application

text: Section 1 These regulations apply to facilities for the disposal of nuclear material and nuclear waste (repositories). The regulations do not apply to facilities for landfill disposal of lowlevel nuclear waste under Section 16 of the Nuclear Activities Ordinance (

text: ). The regulations contain supplementary provisions to the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities.

text: Barriers and their functions

text: Section 2 Safety after the closure of a repository shall be maintained through a system of passive barriers.

text: Section 3 The function of each barrier shall be to, in one or several ways, contribute to the containment and prevention or retention of dispersion of radioactive substances, either directly or indirectly by protecting other barriers in the barrier system.

text: Section 4 A deficiency in any of the repository’s barrier functions that is detected during the construction or operational surveillance of the repository, and that can lead to a deterioration in safety after closure in addition to that anticipated in the safety analysis report, shall be reported to the

text: 1 These regulations and the general advice were issued previously in the Swedish Nuclear Power Inspectorate's Regulatory Code (SKIFS 2002:1). Cf. Chapter 4, Section 2 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities. 1

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: Published on

text: 30 January 2009

text: nuclear material and nuclear waste;

text: issued on 19 December 2008.

text: Application

text: SSMFS 2008:1

text: Barriers and their functions

text: 1 These regulations and the general advice were issued previously in the Swedish Nuclear Power Inspectorate's Regulatory Code (SKIFS 2002:1). 2 Cf. Chapter 4, Section 2 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: Swedish Radiation Safety Authority without unnecessary delay. The same applies if such a deficiency is suspected to occur or if it is suspected that such a deficiency may possibly occur in the future.

text: Design and construction

text: Section 5 The barrier system shall be able to withstand such features, events and processes that can affect the post-closure performance of the barriers.

text: Section 6 The barrier system shall be designed and constructed taking into account the best available technique.

text: Section 7 The barrier system shall comprise several barriers so that, as far as possible, the necessary safety is maintained despite a single deficiency in a barrier.

text: Section 8 The impact on safety of measures adopted to facilitate the monitoring or retrieval of disposed nuclear material or nuclear waste from the repository, or to make access to the repository difficult, shall be analysed and reported to the Swedish Radiation Safety Authority.

text: Safety analysis

text: Section 9 In addition to the provisions contained in Chapter 4, Section 1 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities, the safety analyses shall also comprise features, events and processes that can lead to the dispersion of radioactive substances after closure, and such analyses shall be made before repository construction, before repository operation and before repository closure.

text: Section 10 A safety analysis shall comprise the requisite duration of barrier functions, though a minimum of ten thousand years.

text: Safety analysis reports

text: Section 11 The safety analysis report for a repository shall, in addition to what is required by Chapter 4, Section 2 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities, contain the information shown in Appendix 1 of these regulations and which concerns the period of time following closure. Prior to repository closure, the safety analysis report shall be renewed and subjected to a safety review in accordance with Chapter 4, Section 3 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: 3 Cf. Chapter 2, Section 3 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities. 2 Cf. Chapter 2, Section 3 of the Swedish Environmental Code.

text: concerning safety in nuclear facilities and shall be reviewed and approved by the Swedish Radiation Safety Authority.

text: Exemptions

text: Section 12 If there are particular grounds, the Swedish Radiation Safety Authority may grant exemptions from these regulations if this can be done without circumventing the aim of the regulations and on the condition that safety can be maintained. These regulations enter into force on 1 February 2009.

text: SWEDISH RADIATION SAFETY AUTHORITY

text: ANN-LOUISE EKSBORG Stig Wingefors

text: Swedish Radiation Safety Authority

text: Appendix 1

text: Regulatory Code

text: The following shall be reported with regard to analysis methods: ISSN 2000-0987 Publisher: Ulf Yngvesson - how one or several methods have been used to describe the passive system of barriers in the repository, its performance and evolution over time; the method or methods shall contribute to providing a clear understanding of the features, events and processes that can affect the

text: The Swedish Radiation Safety Authority’s general

text: performance of the barriers and the links between these features, Published on

text: advice on the application of the regulations

text: events and processes 30 January 2009 - how one or several methods have been used to identify and describe (

text: SSMFS 2008:21

text: ) concerning safety in connection relevant scenarios for sequences of events and conditions that can af- with the disposal of nuclear material and nuclear fect the future evolution of the repository; the scenarios shall include a

text: waste;

text: main scenario that takes into account the most probable changes in the repository and its environment issued on 19 December 2008. - the applicability of models, parameter values and other assumptions used for the description and quantification of repository performance The Swedish Radiation Safety Authority hereby issues the following as far as reasonably achievable general advice. - how uncertainties in the description of the barrier system’s functions, scenarios, calculation models and calculation parameters as well as

text: Section 1

text: variations in barrier properties have been dealt with in the safety analysis, including the reporting of a sensitivity analysis showing how According to Section 10 of the Act on Nuclear Activities (

text: ), the the uncertainties affect the description of the evolution of barrier per- holder of a licence to conduct nuclear activities is responsible for ensuring formance and the analysis of the impact on human health and the envi- that the necessary measures are implemented to safely dispose of nuclear ronment waste generated by the activity or nuclear material that is not reused.

text: The following shall be reported with respect to the analysis of post- The Act stipulates that the Government can relieve a licensee of the obliclosure conditions: gations contained in Section 10 of the Act on Nuclear Activities. One condition for being relieved of these obligations is by at the same time - the safety analysis in accordance with Section 9 comprising descripestablishing that the obligations can be fulfilled in a satisfactory manner tions of the evolution in the biosphere, geosphere and repository for by another licensee. selected scenarios; the environmental impact of the repository for selected scenarios, including the main scenario, thereby considering de- According to Section 14 of the Act on Nuclear Activities, licensees retain fects in engineered barriers and other identified uncertainties their obligations to dispose of the nuclear waste and nuclear material in a safe manner until these obligations have been fulfilled. In accordance with Section 16 of the Act on Nuclear Activities, the Swedish Radiation Safety Authority determines whether these obligations are fulfilled. With respect to a repository, this can be achieved after the Swedish Radiation Safety Authority has approved the closure of the repository. As soon as the Swedish Radiation Safety Authority can establish that a licensee has fulfilled its obligations with respect to a repository, the obligation to comply with the provisions contained in these regulations on the part of the repository also ceases.

text: The purpose of the regulations is to promote the safety of a repository so that dispersion of radioactive substances is prevented or delayed. Thus,

text: 1 4 Cf. Section 14 of the Act on Nuclear Activities (

text: ). 1

text: Swedish Radiation Safety Authority

text: Appendix 1

text: Regulatory Code

text: SSMFS 2008:21

text: waste;

text: Section 1

text: ). 1

text: capability of a repository to prevent the dispersion of radioactive substances.

text: An assumption of these regulations is that operational surveillance and maintenance of a repository will be conducted in accordance with the provisions of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities until such time that the repository has been closed. Closure entails backfilling of tunnels and shafts up to ground surface level in accordance with the safety analysis report for the facility (cf. Sections 9 and 11). The backfilling of (for instance) emplacement cavities conducted during the repository operating period (operational backfilling) is not considered to be closure in this respect.

text: The licensee of a repository should ensure that the measures implemented to comply with the requirements on management system, safety review, safety programme and periodic safety review in accordance with the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities are also adequate with respect to postclosure safety.

text: Sections 2 and 3

text: The containment of radioactive substances provided by individual barriers in a repository does not need to be as complete as, for example, that for a leaktight container. Porous materials can also function as barriers through a low permeability to water (low hydraulic conductivity) and substances dissolved in the water (high resistance to diffusion). Parts of the repository or materials in the repository can also be considered barriers without necessarily comprising an obstacle to physical transport. This could for example be the case for materials that contribute to providing a chemical environment counteracting the transport of radioactive substances. Examples of this include a chemical environment that results in low solubility and a high sorption of radioactive substances. ‘Barrier function’ is a term used to designate the different ways that barriers function and the capability of a barrier to protect and preserve the function of other barriers. In this way, a single barrier can have several barrier functions and several barriers can have the same, or similar, barrier functions.

text: Barriers in a repository can be engineered (man-made) or natural.

text: Examples of engineered barriers include containers for nuclear material and nuclear waste, concrete structures and backfill materials consisting of clay, sand or concrete.

text: Examples of engineered barrier functions include mechanical protection of other barriers, complete containment of radioactive substances in leak- 2 tight containers, resistance to water flow and resistance to the diffusion of

text: various substances as well as chemical properties that protect other barriers or help to prevent the dispersion of radioactive materials.

text: The geological formation at the repository site can in itself serve as a natural barrier. The formation (such as rock) can have several barrier functions, for instance isolation of the nuclear waste from the ground surface environment, including rendering human intrusion difficult, limitation of the damaging impact of air and water on engineered barriers, limitation of hydraulic flux in the repository and the contribution to a favourable chemical environment inside and in the vicinity of the repository which counteracts the transport of radioactive substances in the groundwater.

text: The barriers or barrier functions that are necessary in a repository depend on the radioactive inventory of the repository and other substances that affect the safety performance of the barriers and the design and location of the repository. These needs and how they are satisfied by the barrier system should be clearly described in the safety analysis report for the repository in accordance with Sections 9 to 11.

text: The repository site and repository depth should be chosen so that the geological formation provides adequately stable and favourable conditions to ensure that the repository barriers perform as intended over a sufficient period of time. The conditions intended primarily concern temperature-related, hydrological, mechanical (for example, rock mechanics and seismology) and chemical (geochemistry, including groundwater chemistry) factors. Furthermore, the repository site should be located at a secure distance from natural resources exploited today or which may be exploited in the future.

text: Section 4

text: In accordance with the provisions of Chapter 2, Section 10 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities, it is the responsibility of the licensee, for as long as the repository is in operation, to keep continuously informed of the conditions of importance to an assessment of repository safety, also after closure. If, during the continuous analysis and safety assessment, a degradation in barrier performance compared to that stated in the safety analysis report for the facility (in accordance with Chapter 4, Section 2 of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:1

text: ) concerning safety in nuclear facilities) should be detected or suspected after repository closure, the Swedish Radiation Safety Authority should be notified without delay apart from the time required to collect and process the necessary information.

text: Section 6

text: In this context, ‘construction’ means excavation of geological formations (such as rock or soil layers), the construction of facilities above or below ground and the manufacturing, application, control and testing of engineered barriers.

text: The use of the best available technique means that the technology, from a technical and financial standpoint, shall be industrially feasible for application within this area. This means that the technique must be available and not merely exist at an experimental stage. However, the technique need not be available in Sweden (see Government Bill 1997/98:45, Part I, p. 215 ff. for details).

text: Section 7

text: The provision of this Section can be fulfilled by showing in the safety analysis prepared in accordance with Section 9 how different types of deficiencies in barriers and barrier performance cannot on their own lead to unacceptable risks from dispersion of radioactive substances from the repository. It should be possible to show how this dispersion is limited by other barriers and barrier functions besides those affected by the deficiencies that have arisen. In order for the provision to be fulfilled, several barriers may be necessary, especially with respect to the disposal of spent nuclear fuel.

text: Section 8

text: Measures may be adopted during construction and operation for the monitoring of a repository’s integrity and its barrier performance after closure. Such measures can also be adopted to maintain non-proliferation control (‘safeguards’). Measures can also be adopted during construction and operation with the primary aim of facilitating the retrieval of disposed nuclear materials and nuclear waste from the repository, either during the operating period or after closure. Furthermore, measures can be adopted to make intrusion into the repository difficult or to caution against intrusion. The safety analysis report for the facility, in accordance with Section 9, should show that these measures either have a minor and negligible impact on repository safety, or that the measures result in an improvement of safety, compared with the situation that would arise if the measures were not adopted. These provisions are in agreement with the provisions of the Swedish Radiation Safety Authority’s regulations

text: SSMFS 2008:37

text: Section 9 and Appendix

text: The safety of a repository after closure is analysed quantitatively, primarily by estimating the possible dispersion of radioactive substances and how it is distributed over time for a relevant selection of potential future sequences of events (scenarios). The purpose of the safety analysis is to 4 show, inter alia, that the risks from these scenarios are acceptable in rela-

text: tion to the requirements on the protection of human health and the environment imposed by the Swedish Radiation Safety Authority (

text: SSMFS 2008:37

text: ). The safety analysis should also aim to provide a basic understanding of repository performance during different time periods and to identify requirements regarding the performance and design of different repository components.

text: A scenario in the safety analysis comprises a description of how a given combination of external and internal conditions affects repository performance.

text: Two groups of such conditions are: - external conditions in the form of features, events and processes which occur outside repository barriers; these include climate changes and their consequential impact on the repository environment, such as permafrost, glaciation, land subsidence, land uplift as well as the impact of human activities, and - internal conditions in the form of features, events and processes which occur inside the repository; examples of such conditions are properties including defects, nuclear material, nuclear waste and engineered barriers and related processes, as well as properties of the surrounding geological formation and related processes.

text: Based on an analysis of the probability of occurrence of different types of scenarios in different time periods, scenarios with a significant impact on repository performance should be divided into different categories: - main scenario - less probable scenarios - other scenarios or residual scenarios

text: The main scenario should be based on the probable evolution of external conditions and realistic, or where justified, conservative assumptions with respect to the internal conditions. It should comprise future external events which have a significant probability of occurrence or which cannot be shown to have a low probability of occurrence during the period of time covered in the safety analysis. Furthermore, it should as far as possible be based on credible assumptions with respect to internal conditions, including substantiated assumptions concerning the occurrence of manufacturing defects and other imperfections, and which allow for an analysis of the repository barrier performance (for example, it is insufficient to always base the analysis on leaktight waste containers over an extended period of time, even if this can be shown to be the most probable case). The main scenario should be used as the starting point when analysing the impact of uncertainties (see below), which means that the analysis of the main scenario also includes a number of calculation cases.

text: Less probable scenarios should be prepared for the evaluation of scenario uncertainty (see also below). This includes variations of the main scenario with alternative sequences of events and periods of time as well as scenarios that take into account the impact of future human activities, such as damage inflicted on barriers. (Detriment to humans intruding into the repository is illustrated by residual scenarios; see below.) An analysis of less probable scenarios should include analyses of uncertainties that are not evaluated within the framework of the main scenario.

text: Residual scenarios should include sequences of events and conditions that are selected and studied independently of probabilities in order to, inter alia, illustrate the significance of individual barriers and barrier functions. The residual scenarios should also include cases to illustrate detriment to humans intruding into the repository as well as cases to illustrate the consequences of an unclosed repository that is not monitored.

text: Lack of knowledge and other uncertainties in the calculation presumptions (assumptions, models, data) are in this context denoted as uncertainties. These uncertainties can be classified as follows: - scenario uncertainty: uncertainty with respect to external and internal conditions in terms of type, degree and time sequence - system uncertainty: uncertainty as to the completeness of the description of the system of features, events and processes used in the analysis of both individual barrier performance and the performance of the repository as a whole - model uncertainty: uncertainty in the calculation models used in the analysis - parameter uncertainty: uncertainty in the parameter values (input data) used in the calculations - spatial variation in the parameters used to describe the barrier performance of the rock (primarily with respect to hydraulic, mechanical and chemical conditions)

text: There are often no clear boundaries between the different types of uncertainties. The most important requirement is that the uncertainties are to be described and handled in a consistent and structured manner.

text: The evaluation of uncertainties is an important part of the safety analysis. This means that uncertainties should be discussed and examined in depth when selecting calculation cases, calculation models and parameter values, as well as in the assessment of calculation results.

text: The assumptions and calculation models used should be carefully selected with respect to the principle that the application and selection should be justified by means of a discussion of alternatives and with reference to science. In cases where there is doubt as to the applicability of a model, 6

text: several models should be used to illustrate the impact of the uncertainty involved in the choice of model.

text: Both deterministic and probabilistic methods should be used so that they complement each other and, consequently, provide as comprehensive a picture of the risks as possible.

text: The probabilities of the scenarios and calculation cases actually occurring should be estimated as far as possible in order to calculate risk. Such estimates cannot be exact. Consequently, the estimates should be substantiated through the use of several methods, for example assessments by several independent experts. This can for instance be done through estimates of when different events can be expected to have occurred.

text: A number of design basis cases should be identified based on scenarios that can be shown to be especially important from the standpoint of risk. Together with other information, such as regarding manufacturing method and controllability, these cases should be used to substantiate the design basis, such as requirements on barrier properties.

text: Particularly in the case of disposal of nuclear material, for example spent nuclear fuel, it should be demonstrated that criticality cannot occur in the initial configuration of the nuclear material. With respect to the redistribution of the nuclear material through physical and chemical processes, which can lead to criticality, it should be demonstrated that such redistribution is very improbable.

text: The result of calculations in the safety analysis should contain such information and should be presented in such a way that an overall judgement of safety compliance with the requirements can be made.

text: The validity of assumptions used, such as models and parameter values, should be supported, for example by citing references to scientific literature, special investigations and research results, laboratory experiments on different scales, field experiments and studies of natural phenomena (natural analogues).

text: Scientific background material, such as from expert assessments, should be documented in a traceable manner by conscientiously referring to scientific literature and other material.

text: Section 10

text: The time period for which safety needs to be maintained and demonstrated should be a starting point for the safety analysis. One way of discussing and justifying the establishment of the relevant time period is to start from a comparison of the hazard of the radioactive inventory of the repository with the hazard of radioactive substances occurring in nature. How- 7

text: ever, it should also be possible to take into consideration the difficulties of conducting meaningful analyses for extremely long periods of time, beyond one million years, in some other way than by demonstrating how the hazard of the radioactive substances in the repository declines over time.

text: In the case of a repository intended for long-lived waste, the safety analysis may need to include scenarios taking greater expected climate changes into account, primarily in the form of future glaciations. For example, the next complete glacial cycle, currently estimated to be in the order of 100,000 years, should be particularly taken into account.

text: In the case of periods up to 1,000 years after closure, in accordance with the provisions of

text: SSMFS 2008:37

text: , the dose and risk calculated for current conditions in the biosphere constitute the basis for assessing repository safety and the repository’s protective capabilities.

text: Furthermore, in the case of more extended periods of time, the assessment can be made using dose as one of several safety indicators. This should be taken into account in connection with calculations as well as presentation of analysis results. Examples of these supplementary safety indicators include the concentrations of radioactive substances from the repository which can build up in soils and near-surface groundwater as well as the calculated flow of radioactive substances to the biosphere.

text: This general advice applies as of 1 February 2009.

text: SWEDISH RADIATION SAFETY AUTHORITY

text: ANN-LOUISE EKSBORG

text: Stig Wingefors

text: SSMFS 2008:37

text: SWEDISH RADIATION SAFETY AUTHORITY

text: ANN-LOUISE EKSBORG

text: Stig Wingefors


text: Swedish Radiation Safety Authority Regulatory Code

text: ISSN: 2000-0987

text: 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

text: Please note that translated versions of the Authority’s regulations lack legal force and are for information purposes only.

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: The Swedish Radiation Safety Authority's

text: Published on 30 January

text: certain Nuclear Facilities;

text: issued on 19 December 2008.

text: On the basis of Section 7 of the Radiation Protection Ordinance (

text: ), the Swedish Radiation Safety Authority hereby issues the following regulations.

text: Application and definitions

text: Section 1 These regulations apply to the following nuclear facilities for which the Government has granted licences under the Nuclear Activities Act (

text: ): 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 (

text: ), 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 (

text: SSMFS 2008:37

text: ) on the protection of human health and the environment in connection with the final management of spent nuclear fuel and nuclear waste.

text: 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

text: Definitions Rules of consideration and protection of human

text: Section 2 In these regulations the following terms and concepts are used health and the environment

text: 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.

text: 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

text: 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

text: 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.

text: 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.

text: 2 3

text: Rules of consideration and protection of human health and the environment

text: 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.

text: 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.

text: 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.

text: 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

text: 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.

text: General provisions

text: Section 7 Environmental surveillance shall be performed at nuclear facilities.

text: 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.

text: 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.

text: 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.

text: 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.

text: Discharge surveillance

text: 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.

text: 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.

text: 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.

text: 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.

text: 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.

text: 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

text: 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.

text: 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.

text: 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.

text: Environment checks

text: Section 20 Environment checks shall be conducted in the vicinity of a nuclear facility according to a scheme 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.

text: 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.

text: Section 23 Continual registration of meteorological conditions shall be made at nuclear power reactors and reactors for research or materials testing.

text: Reporting

text: 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.

text: 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.

text: Section 28 Events leading to increased discharge of radioactive substanc-

text: Environment checks

text: es 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 scheme 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

text: 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

text: Section 23 Continual registration of meteorological conditions shall be Ann-Christin Hägg made at nuclear power reactors and reactors for research or materials testing.

text: Reporting

text: 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

text: Appendix 1

text: 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.

text: 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.

text: 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.

text: Appendix 1 Appendix 2

text: Environment checks

text: 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.

text: 8 9


text: Swedish Radiation Safety Authority Regulatory Code

text: ISSN: 2000-0987 SSMFS: 2008:24

text: The Swedish Radiation Safety Authority’s Regulations on Radiation Protection Managers at Nuclear Facilities

text: Please note that translated versions of the Authority’s regulations lack legal force and are for information purposes only.

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: Published on 30 January

text: Regulations on Radiation Protection Managers 2009

text: at Nuclear Facilities;

text: issued on 19 December 2008.

text: On the basis of Section 7 of the Radiation Protection Ordinance (

text: ), the Swedish Radiation Safety Authority hereby issues the following regulations.

text: Application

text: Section 1 These regulations apply to radiation protection managers at nuclear facilities.

text: Section 2 Terms and concepts in these regulations have the same meanings as used in the Radiation Protection Act (

text: ) and the Act on Nuclear Activities (

text: Competence and organisation

text: Section 3 The licence holder shall appoint a radiation protection manager and a substitute for this manager at the nuclear facility. These persons shall be approved by the Swedish Radiation Safety Authority. The radiation protection manager shall possess sufficient competence on matters of significance to radiation protection. In order to be approved, documents on the competence of the intended manager shall be presented to the Swedish Radiation Safety Authority.

text: 1 These regulations were issued previously in the Swedish Radiation Protection Authority’s Regulatory Code (SSI FS 2000:11). 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 L 159, 29/06/1996, p. 1 (Celex 31996L0029). 3 See the Swedish Radiation Safety Authority’s general advice (

text: SSMFS 2008:29

text: ) on the competence of radiation protection experts. This general advice explains the content of the European Commission’s Communication concerning ‘qualified experts’ (OJ C 133 dated 30 April 1998) on implementation of Council Directive 96/29/Euratom. 1

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: Published on 30 January

text: at Nuclear Facilities;

text: issued on 19 December 2008.

text: Application

text: ) and the Act on Nuclear Activities (

text: Competence and organisation

text: 1 These regulations were issued previously in the Swedish Radiation Protection Authority’s Regulatory Code (SSI FS 2000:11). 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 L 159, 29/06/1996, p. 1 (Celex 31996L0029). See the Swedish Radiation Safety Authority’s general advice (

text: SSMFS 2008:29

text: Tasks

text: Section 4 The manager shall: 1. be the qualified expert on radiation protection at the facility, 2. actively work for compliance with the provisions contained in the Radiation Protection Act as well as other applicable regulations and conditions, 3. actively promote work at the facility being performed at an acceptable level from the point of view of radiation protection, 4. ensure that local rules are established in order to prevent unacceptable or unnecessary exposure of individuals to ionising radiation, 5. ensure that individual and collective doses are followed up, 6. monitor matters for radiation protection at the facility relating to competence and resources, 7. ensure that events and observations of significance to radiation protection are analysed and recorded and that such information is provided to the Swedish Radiation Safety Authority, 8. ensure that the requirements on reporting are fulfilled, and 9. serve as a contact person for the Swedish Radiation Safety Authority.

text: Exemptions

text: Section 5 If there are particular grounds, the Swedish Radiation Safety Authority may grant exemptions from these regulations if this can be done without circumventing the aim of the regulations.

text: These regulations enter into force on 1 February 2009.

text: Managers who are approved at the point in time when these regulations enter into force may continue with their work.

text: SWEDISH RADIATION SAFETY AUTHORITY

text: ANN-LOUISE EKSBORG

text: Peter Hofvander


text: ISSN: 2000-0987

text: The Swedish Radiation Safety Authority’s Regulations on Radiation Protection of Individuals Exposed to Ionising Radiation at Nuclear Facilities

text: ISSN 2000-0987 Publisher: Ulf Yngvesson

text: The Swedish Radiation Safety Authority’s

text: Regulations on Radiation Protection of Published on 30 January

text: Individuals Exposed to Ionising Radiation

text: at Nuclear Facilities;

text: issued on 19 December 2008.

text: Application and definitions

text: Section 1 These regulations are applicable to radiation protection of individuals at nuclear facilities.

text: Section 2 Terms and concepts used in the Radiation Protection Act (

text: ) and the Act on Nuclear Activities (

text: ) have the same meanings in these regulations.

text: Section 3 In these regulations the following concepts are used with the meanings specified here.

text: effective dose: weighted radiation dose regarding the biological effects of the type of radiation as well as the sensitivity of various organs external exposure: exposure to a source situated outside the human body external contamina- radioactive substances on the human body or tion: on clothing whole body counting: measurement of the content of radioactive substances in the human body using one or more detectors

text: 1 These regulations were issued previously in the Swedish Radiation Protection Authority's Regulatory Code (SSI FS 2000:10). 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 L 159, 29/06/1996, p. 1 (Celex 31996L0029). 1

text: committed effective the total effective dose, integrated over 50 dose: years, after an intake of radioactive substances into the human body internal exposure: exposure to radioactive substances within the human body internal contamina- radioactive substances in the human body after tion: an intake by inhalation, through the digestive system or through the skin calibration: measures in order to determine, under specified conditions, the relationship between the reading of an instrument and the corresponding true value of a quantity collective dose: the mean radiation dose to a group of individuals multiplied by the number of individuals in the group individual dose: a generic term for effective dose and committed effective dose individual dose meter: an instrument containing one or more detectors used for individual monitoring of external exposure

text: Optimisation of radiation protection

text: Section 4 Work activities at a nuclear facility shall be performed in such a way that doses to individuals are kept as low as reasonably achievable, with economic and societal factors being taken into account. For this purpose, the licence holder shall ensure that goals and needed means for control are defined and documented and that the necessary resources are available.

text: Section 5 The goals and means for control shall be adapted with respect to the prerequisites of the plant and be defined to take into account both daily and long-term radiation protection. All individuals who are exposed to radiation in their work or who are decision-makers in matters that may affect the individual doses of workers shall have knowledge regarding the relevant goals and means for control to the extent this is pertinent to them. The work activities, including goals and means for control, shall be followed up and evaluated with respect to the provisions of Section 4. Such evaluation shall be conducted at least once a year. Documentation on the evaluation shall be sent to the Swedish Radiation Safety Authority.

text: committed effective the total effective dose, integrated over 50

text: Information and training

text: dose: years, after an intake of radioactive substances Section 6 All personnel, including the plant’s own personnel as well as into the human body outside workers, shall be informed about radiation protection prior to internal exposure: exposure to radioactive substances within the work within a supervised or controlled area. Refresher courses on the

text: human body relevant information shall be held thereafter at least once every third year.

text: internal contamina- radioactive substances in the human body after The information shall include a survey of the risks related to work

text: tion: an intake by inhalation, through the digestive with ionising radiation, how to act in the event of an alarm, the local in-

text: system or through the skin structions and routines at the plant and practical aspects of radiation pro-

text: tection. calibration: measures in order to determine, under specified In addition to the information on radiation protection mentioned in the conditions, the relationship between the readfirst and second clauses, special training may in certain cases be required. ing of an instrument and the corresponding true The scope and focus of such training shall be adapted with respect to the value of a quantity kind of work and to the environment where the work is to be performed. collective dose: the mean radiation dose to a group of individu-

text: als multiplied by the number of individuals in Section 7 All personnel working with matters related to radiation protec-

text: the group tion, the plant’s own personnel working in the area of operation or

text: individual dose: a generic term for effective dose and commit- maintenance as well as outside workers holding posts as foremen, shall

text: ted effective dose have undergone an in-depth training programme which, for example,

text: encompasses the fundamental principles of radiation protection. individual dose meter: an instrument containing one or more detectors The training programme shall be adapted with respect to the kind and used for individual monitoring of external extent of the work as well as the environment where the work is to be exposure performed.

text: Refresher courses on radiation protection shall be held to the extent

text: necessary.

text: Optimisation of radiation protection

text: Section 4 Work activities at a nuclear facility shall be performed in such a Section 8 Details on the latest occasion when information or training was way that doses to individuals are kept as low as reasonably achievable, provided relating to radiation protection to each individual shall be docuwith economic and societal factors being taken into account. For this mented with respect to the extent and date of such information or training. purpose, the licence holder shall ensure that goals and needed means for

text: control are defined and documented and that the necessary resources are 4

text: Medical examination

text: available.

text: Section 9 A medical examination of a worker from a country outside the

text: Section 5 The goals and means for control shall be adapted with respect European Union, performed in a foreign country, may be accepted if the

text: to the prerequisites of the plant and be defined to take into account both outcome of such examination can be verified.

text: daily and long-term radiation protection. All individuals who are exposed

text: to radiation in their work or who are decision-makers in matters that may

text: Local radiation protection instructions

text: affect the individual doses of workers shall have knowledge regarding the Section 10 The licence holder shall ensure that local radiation protection relevant goals and means for control to the extent this is pertinent to them. instructions are established. The work activities, including goals and means for control, shall be These shall at least comprise the plant’s internal instructions and roufollowed up and evaluated with respect to the provisions of Section 4. tines for: Such evaluation shall be conducted at least once a year. Documentation 1. categorisation of workers, on the evaluation shall be sent to the Swedish Radiation Safety Authority. 2. controlled areas,

text: 3 See the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) concerning basic provisions for the protection of workers and the general public in practices involving ionising radiation. 4 2 Ibid. 3

text: 3. training on radiation protection, 4. monitoring of individual doses, 5. contamination checks, 6. calibration and checks of instruments and equipment, 7. handling and transport of radioactive substances within the plant, 8. visitors within a controlled area, 9. documentation, and 10. reporting.

text: Controlled areas

text: Section 11 Within a controlled area, premises and places where the risk of receiving a yearly effective dose exceeding 50 mSv is not negligible shall be especially marked. Admittance shall be especially restricted to this type of location.

text: Section 12 Within a controlled area, food consumption and smoking shall be forbidden. Water shall only be available from a drinking fountain or be served within special areas according to the provisions of Section 13. Prior to the establishment of such an area, a description of the area and its intended use, including a programme for contamination checks, shall be sent to the Swedish Radiation Safety Authority for consideration.

text: Section 13 The following conditions shall apply when serving beverages in a special area a) Before entrance to the area, all persons shall be checked for contamination and must be free from external contamination according to the requirements stipulated in Section 20. b) Beverages shall only be served in a disposable package or in a disposable cup filled directly from a machine. c) The surface contamination within the area must not exceed 40 kBq/m² as summed up for the most common beta- and gamma-emitting nuclides, or must not exceed 4 kBq/m² for alpha-emitting nuclides. The surface contamination must be verified regularly by means of contamination checks in the area.

text: Section 14 For the purpose of showing that the provisions concerning categorisation of workplaces are met, monitoring of the environment outside the controlled area shall be performed by: 1. measuring gamma radiation with the aid of stationary dosimeters, and 2. checking for surface contamination of a sample of floor and ground, performed at least once a year.

text: Visitors

text: Section 15 Visitors from the general public are only permitted in a controlled area if guided by an authorised person and if a pre-approved plan is followed. It shall be the radiation protection manager who decides which persons are authorised and which persons have the authority to approve plans.

text: Section 16 Visitors from the general public must be at least 14 years old to be allowed admittance to a controlled area. School classes of at least the eighth school year may be allowed admittance as visitors regardless of the age of the pupils.

text: Monitoring of individual doses

text: External exposure

text: Section 17 All personnel, both the plant’s own personnel as well as outside workers, shall, when present within a controlled area, carry an individual dose meter that fulfils the requirements as stipulated in the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) concerning basic provisions for the protection of workers and the general public in practices involving ionising radiation. When present in areas with radiation levels where there is a risk of a dose limit being exceeded, an instrument shall be carried that immediately indicates the accumulated dose and which is provided with an alarm function, regardless of other kinds of individual dose meter to be carried. If, in addition, there is a risk of rapid changes in the dose rate, the instrument shall have an alarm function regarding dose rate.

text: Section 18 Visitors within a controlled area shall carry an individual dose meter. In a guided group of visitors, it is sufficient if two persons in the group carry individual dose meters. The recorded dose shall be valid for all individuals in the group. The individual dose meters may be of a type that gives an immediate reading.

text: External and internal contamination

text: Section 19 All persons within a controlled area which is classified with respect to surface or air contamination shall undergo contamination checks before leaving the area.

text: 5 Not within the scope of the Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) concerning basic provisions for the protection of workers and the general public in practices involving ionising radiation in terms of monitoring and reporting of radiation doses. 5

text: Section 20 An individual shall be regarded as free from external contamination if the surface contamination, calculated as the mean over an area of 0.01 m², does not exceed 40 kBq/m² as summed up for the most common beta- and gamma-emitting nuclides and does not exceed 4 kBq/m² for alpha-emitting nuclides. Checks for alpha-emitting nuclides are not needed when exiting the area if there are other means to verify that alpha contamination is very unlikely.

text: Section 21 If there are reasons to suspect that individuals have been internally contaminated, or if internal contamination is confirmed, they shall undergo whole body counting. Whole body counting shall be performed on a sample of individuals who have worked in environments where it is considered that there is a particular risk of intake of radioactive substances. Thus, at least one individual from each team shall undergo whole body counting at the end of the working period or after the work has been completed. In the case of long-term work, such measurement shall be performed at least once a month. If an intake that is calculated to imply a committed effective dose of 0.25 mSv or more is found, the whole team shall be measured. Whole body counting shall be performed for a reference group, in the first instance consisting of own personnel mainly working within a controlled area. The sample for the reference group shall be representative for the practice and the individuals in the group shall be measured at least four times a year.

text: Section 22 Whole body counting shall be performed according to a documented procedure approved by the Swedish Radiation Safety Authority. The documentation shall show: 1. the measurement equipment and routines for its use, 2. the competence of the personnel performing the measurements, 3. methods used for calculating the intake and the committed effective doses, 4. routines for evaluating and assessing the measurement results obtained, and 5. routines for calibrations and checks of the measurement equipment.

text: Instruments and equipment

text: Section 23 Instruments and equipment used for measurements of: 1. individual doses from external exposure, 2. contamination (external, internal or on surfaces), 3. dose rate, 4. airborne activity, and 5. smear tests shall be calibrated and undergo function checks at regular intervals.

text: Section 24 Instruments intended for measurements of dose rate shall be calibrated towards a reference source. The dose rates in the calibration set-up shall, at least every second year, be checked against an instrument that is calibrated at a test house that is accredited for ionising radiation. Alternatively, the instrument may be calibrated directly at an accredited test house.

text: Section 25 Calibrations and checks of equipment for determining internal contamination shall be performed for the nuclides expected to be present. The measurement tolerances, limits of detection and the geometry used in measurements shall be documented.

text: Section 26 Written instructions for the use, calibration and checks of all types of instruments and equipment mentioned in Section 23 shall be established.

text: Transport within the plant

text: Section 27 Transports of radioactive substances within one’s own plant but outside a controlled area shall, to the most practical extent, be performed in accordance with the applicable provisions concerning transport of hazardous goods on public roads as regards the requirements concerning dose rate, surface contamination and packaging.

text: Work with irradiated fuel elements

text: Section 28 Work with dismounting of irradiated fuel elements at a nuclear power reactor where single fuel rods are handled must not commence earlier than five days after the reactor has been placed in ‘cold shutdown mode’. During work with the single fuel rods, only persons directly involved in the work may be present.

text: Section 29 Air monitoring shall be performed continuously at the working position during the work involving fuel dismounting. The equipment used for monitoring shall be designed to enable checking for any leakage from the fuel and be provided with an alarm. The working position shall be protected by an air flow directed away from the position.

text: Section 30 Documented instructions for the alarm and evacuation procedures for the premises shall be available. These instructions shall be well known to all persons working in the premises.

text: 6 For transport of radioactive substances, regulations issued by the Swedish Rescue Services Agency apply on the basis of the Transport of Hazardous Goods Act (

text: ). ADR applies to transport by public road. 7 As defined by the respective nuclear power plant’s Operational Limits and Conditions ('STF'). 7

text: Section 36 Any internal contamination occurring at one single event

text: Fuel damage

text: which is calculated to give a committed effective dose of 5 mSv or more Section 31 A documented policy for dealing with fuel damage shall be shall be reported in writing to the Swedish Radiation Safety Authority. established at all plants where nuclear power reactors are involved. The The report shall comprise the type of intake, the calculated committed policy shall include a description of the plant’s strategy for avoiding fuel effective dose and the basis for these calculations, as well as the cause and damage as far as possible. A strategy shall also be in place for dealing circumstances of the internal contamination. The report shall be sent as with a situation should fuel damage occur. soon as possible after the contamination has been found.

text: Reporting Section 37 The Swedish Radiation Safety Authority shall be informed

text: Section 32 The provisions of Chapter 5, Section 3 and Sections 9 to 11 of about events or observations that are significant from a radiation protecthe Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) tion point of view. concerning basic provisions for the protection of workers and the general If an event has occurred which has implied, or could have implied, public in practices involving ionising radiation shall not apply to nuclear that any given dose limit is exceeded, a report shall be sent to the Swefacilities, but are replaced by Sections 33 to 39 of these regulations. dish Radiation Safety Authority as soon as possible.

text: Section 33 An annual written report shall be submitted to the Swedish Documentation and filing of measurement data

text: Radiation Safety Authority containing a compilation of the radiation dos-

text: Individual doses

text: es to the personnel as well as the results of the radiation surveillance per- Section 38 Primary data on evaluations of individual doses due to exterformed outside the controlled area. The report shall be submitted not later nal as well as internal exposure shall be kept at least one year after the than two months after the turn of the calendar year covered by the report. calendar year when the measurements were conducted. The scope and structure of this report are decided by the Swedish Radiation Safety Authority. Section 39 The final results from the evaluation of individual doses due to external as well as internal exposure shall be able to relate to every Section 34 Work activities where the total collective dose is expected to single person and be available in a central register approved by the Sweexceed 100 millimansievert (mmanSv) shall be notified in advance, in dish Radiation Safety Authority. writing, to the Swedish Radiation Safety Authority. The following proce- The final results from the evaluation of individual doses due to exterdures apply: nal exposure do not need to be recorded if the monthly doses, or alternaa) The Swedish Radiation Safety Authority shall be notified four tively, doses within periods of four weeks, are less than 0.1 mSv. months before the work commences. The information shall comprise a survey of the work and an estimation of the expected radiation doses to the personnel. Other situations

text: b) Advance notification shall be sent to the Swedish Radiation Safety Section 40 The results from the radiation surveillance outside controlled Authority four weeks before the works commence. Such notification shall areas according to Section 14 shall be documented and kept at least one comprise a forecast of doses in terms of the entire scope of work, the year after the end of the calendar year when the measurements were condifferent steps of the work and the doses to particularly exposed groups of ducted. workers. Such notification shall also include an account of the considerations made concerning radiation protection. Section 41 The results of the latest performed calibration and subsequent c) If significant changes take place in relation to the plans presented in checks according to Sections 23 to 25 shall be documented and kept at the notification, a revised version shall be sent to the Swedish Radiation least one year after the end of the calendar year when the calibration re- Safety Authority as soon as possible. sults were most recently used.

text: Section 35 Not later than three months after the work is finished and where the total collective dose has exceeded 100 mmanSv, a written report shall be sent to the Swedish Radiation Safety Authority comprising 8 The Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) concerning basic the experiences gained in terms of radiation protection matters. provisions for the protection of workers and the general public in practices involving ionising radiation. 8 9

text: Section 36 Any internal contamination occurring at one single event which is calculated to give a committed effective dose of 5 mSv or more shall be reported in writing to the Swedish Radiation Safety Authority. The report shall comprise the type of intake, the calculated committed effective dose and the basis for these calculations, as well as the cause and circumstances of the internal contamination. The report shall be sent as soon as possible after the contamination has been found.

text: Section 37 The Swedish Radiation Safety Authority shall be informed about events or observations that are significant from a radiation protection point of view. If an event has occurred which has implied, or could have implied, that any given dose limit is exceeded, a report shall be sent to the Swedish Radiation Safety Authority as soon as possible.

text: Documentation and filing of measurement data

text: Individual doses

text: Section 38 Primary data on evaluations of individual doses due to external as well as internal exposure shall be kept at least one year after the calendar year when the measurements were conducted.

text: Section 39 The final results from the evaluation of individual doses due to external as well as internal exposure shall be able to relate to every single person and be available in a central register approved by the Swedish Radiation Safety Authority. The final results from the evaluation of individual doses due to external exposure do not need to be recorded if the monthly doses, or alternatively, doses within periods of four weeks, are less than 0.1 mSv.

text: Other situations

text: Section 40 The results from the radiation surveillance outside controlled areas according to Section 14 shall be documented and kept at least one year after the end of the calendar year when the measurements were conducted.

text: Section 41 The results of the latest performed calibration and subsequent checks according to Sections 23 to 25 shall be documented and kept at least one year after the end of the calendar year when the calibration results were most recently used.

text: 8 The Swedish Radiation Safety Authority’s regulations (

text: SSMFS 2008:51

text: ) concerning basic provisions for the protection of workers and the general public in practices involving ionising radiation. 9

text: Exemptions

text: Section 42 If there are particular grounds, the Swedish Radiation Safety Authority may grant exemptions from these regulations if this can be done without circumventing the aim of the regulations. These regulations enter into force on 1 February 2009. SWEDISH RADIATION SAFETY AUTHORITY ANN-LOUISE EKSBORG Peter Hofvander