Experience of Morocco: existing facility

Transcription

1 Experience of Morocco: existing facility Abderrahim BOUIH 1

2 Contents Introduction Legal framework Safety analysis of the installation Perspective 2

3 Introduction The radioactive waste management installation is considered as an installation for protecting the environment Since the installation is built in a nuclear center, the regulatory body requests a Safety Analysis Report where it is shown in both normal and accidental situations that the installation has no impact on the environment 3

4 Regulatory frame work Regulation Law No of 12 October 1971 Dahir No of May 19, 2000 Law No may 2003 on environmental impact study Decree of 7 December 1994 Decree No October 1997 Description On the protection against ionizing radiation publishing the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management made in September 29, 1997 The law aims to precede the realization of certain installations by an assessment of their impact on the environment. Relating to the licensing and control of nuclear facilities Made for the implementation of Law No on the protection against ionizing radiation 4

5 Licensing and authorization for nuclear installation A licensing system for nuclear facilities is described by the decree number of 7 December 1994 After consultation with the National Commission of Nuclear Safety, the Ministry of Energy, Mines, Environment and Water gives authorizations for: Construction of nuclear installation Discharging of liquid and gas effluents to the environment Commissioning Operation Decommissioning All these authorizations are delivered base on safety analysis report Safety Analysis Report is a document provided by the applicant or holder, containing information about the nuclear facility and its design, accident analysis and precautions taken to minimize the risk to the public, environment and site personnel 5

6 Licensing phases document needed Time Authorization required Preliminary safety analysis report: Evaluation of the site Radiological background Density and population distribution Impact study sitting and evaluation of site Construction of CENM Construction authorization Document providing information about systems intended for the treatment of liquid and gas in order to maintain the quantity and concentration of radioactive releases within prescribed limits preliminary safety analysis report which supplements and updates the previous one The design of the nuclear installation and operating procedures of the facility; The study of the facility as constructed; Analysis of hypothetical accidents and the ability of safety systems to limit the consequences final safety analysis report commissioning results limits and operating conditions The operating programs and detailed operating procedures of the plant 2001 to 2005 Authorization to discharge radioactive effluent, liquid or gaseous Commissioning authorization Operating authorization 6

7 Safety Analysis Report The safety analysis report is prepared in such a way to focus on the accident situation to assess the impact of the facility on the man and his environment The impact study is made for penalizing meteorological conditions and for weather of the center In this report, we consider radiological hazards as well as the non radiological risks. We give only a qualitative analysis and a description of the technical and administrative means to prevent and mitigate those risks The report doesn t include a safety analysis of the system of the management of radioactive waste management The risks associated to the management of different type of waste are described in system notes but not assessed 7

8 Impact study Impact on the environment In normal operation, the release expected is about 35 m3 of treated effluent with a residual activity concentration of 10 Bq / l In accidental operation, design basis accidents that must be taken into account are: Fire in the storage drums of solid waste not cemented. The maximum activity to consider in this case is GBq (volume: 612 barrels, and activity concentration of 0.37 GBq / m3) Transport accident of liquid effluents: The maximum activity to consider is 5 MBq. 8

9 Impact study Impact on the public Accidental scenario used is based on taking fire of drum of compactable solid waste not cemented into the storage area For the evaluation of the consequences of the fire, it is assumed that the fire damaged all drums stored in the cell and all waste is burnt and dispersed in the smoke 9

10 Assessment of radiological consequences Penalizing meteorological situations Area concerned Weather condition CTA max (s.m -3 ) Integrated Doses Effective inhalation (Sv) Inhalation thyroid (Sv) Submersion plume (Sv) 10m-50m ND10 7,00E-02 1,46E-02 1,25E-03 1,29E-04 50m-100m ND10 4,50E-03 9,40E-04 8,05E-05 8,30E m-1km ND10 1,50E-03 3,13E-04 2,68E-05 2,77E-06 1km-2km LD5 1,30E-04 2,71E-05 2,32E-06 2,40E-07 2km-5km LD5 4,00E-05 8,35E-06 7,15E-07 7,38E-08 5km-10km LD5 9,00E-06 1,88E-06 1,61E-07 1,66E-08 >10km LD5 3,00E-06 6,26E-07 5,37E-08 5,53E-09 CTA: Atmospheric Transfer Coefficient ND10: Normal Diffusion 10: wind speed LD : Low Diffusion 10

11 Assessment of radiological consequences Actual weather conditions prevailing at the site of the CEN Weather CTA max (LD 1.2) Area concerned (s.m -3 ) integrated Doses Effective inhalation (Sv) Inhalation thyroid (Sv) Panache (Sv) 10m-50m 3,50E-02 7,31E-03 6,26E-04 6,46E-05 50m-100m 4,00E-03 8,35E-04 7,15E-05 7,38E m-1km 1,60E-03 3,34E-04 2,86E-05 2,95E-06 1km-2km 4,50E-05 9,39E-06 8,05E-07 8,30E-08 2km-5km 1,50E-05 3,13E-06 2,68E-07 2,77E-08 5km-10km 3,30E-06 6,89E-07 5,90E-08 6,09E-09 D>10km 1,00E-06 2,09E-07 1,79E-08 1,84E-09 11

12 Assessment of radiological consequences Dose estimates for different routes of exposure, due to the accident reference in Radioactive Waste facility Weather (LD 2.5) CTA max Integrated Doses Area concerned (s.m -3 ) Effective inhalation (Sv) Inhalation thyroid (Sv) Panache (Sv) 10m-50m 2,5E-02 5,22E-03 4,47E-04 4,61E-05 50m-100m 1,80E-03 3,76E-04 3,22E-05 3,32E m-1km 5,50E-04 5,96E-04 9,84E-06 1,01E-06 1km-2km 1,20E-05 1,30E-05 2,15E-07 2,21E-08 2km-5km 3,00E-06 3,25E-06 5,37E-08 5,53E-09 5km-10km 6,00E-07 6,50E-07 1,07E-08 1,11E-09 D>10km 1,80E-07 1,95E-07 3,22E-09 3,32E-10 12

13 Assessment of radiological consequences Compared with regulatory exposure limits for members of the public, integrated doses evaluated following the accidental fire situation, are well below those limits. A safety case was developed for the management of DSRS under the project INT9/176 with the help of NECSA 13

14 Perspectives We plan to extend the elaboration of the safety case to management of the other waste using SAFRAN software to calculate the released dose for different scenarios of accident that could happened while we manage the waste 14

15 Thanks for your attention 15