1. National Nuclear Energy Commission Brazil’s Regulatory Body

2. Report on the Regulatory Activities in Brazil Legislative Framework for Conformity with IAEA Safety Standards Programme Altair Souza de Assis, Ph.D. Director of Radiation Protection and Nuclear Safety and Security
Commission on Safety Standards Eighteenth Meeting 28 – 29 November 2005 IAEA Headquarters, Vienna - Austria

3. Regulatory Activities in Brazil
I CONFORMITY WITH IAEA SAFETY STANDARDS
(Development and Application of the IAEA Safety Standards)
II REGULATORY HIGHLIGHTS IN 2005

4. I CONFORMITY WITH IAEA SAFETY STANDARDS
Legislative Framework
CNEN Standards are officially issued through a resolution of its Deliberative Commission, which is constituted by CNEN’s President , three directors (Safety and Security, Research and Development and Institutional Management) and an external member representing society. The standards elaboration process is performed according to the documented procedure, with the participation of experts in several disciplines pertinent to the subject in matter, involving the several areas of the Commission.

5. THE REGULATORY POSITIONS
CNEN Standards define the requirements, which shall be attended to ensure that the safety and security purposes are satisfied. These standards do not define how something can be done, thus, in certain cases, CNEN Standards only contain some requirements of general character. In special situations, it is necessary a formal interpretation of some requirements as well as some additional information of acceptable ways to accomplish them. For that purpose, in 1999 the “Regulatory Positions” were created according to the documented procedures and since then they have been regularly issued by CNEN’s Radioprotection and Nuclear Safety Directory. They speed up regulatory control and work as a “bridge” between CNEN Standards and other reference documents, in particular those of the IAEA.

6. REFERENCES
In 1974, the first department responsible for the coordination of CNEN Standards elaboration (the old Specifications and Standards Department) was constituted. In this period, the first Brazilian nuclear power plant, Angra I, a Westinghouse PWR design, was built. Thus, the establishment of CNEN Standards was highly influenced by this fact, which was reflected on the first standard documents based on the American nuclear standards system, in particular for the facilities and activities related to nuclear reactors and, subsequently, for the fuel cycle facilities. For areas such as the Quality Assurance and Radiological Protection, the IAEA documents were used from the very beginning.
The following list presents, for further details, the use of IAEA reference documents on the development of CNEN Standards:

7. IAEA RERERENCE DOCUMENTS
1. CURRENT STANDARDS AND REGULATORY POSITIONS
CNEN-NE-1.09: “STANDARD MODEL FOR SAFETY ANALYSIS REPORT OF FUEL ELEMENTS MILLS”
IAEA Reference Document:
Code 50-C-QA: “Code on the Safety of Nuclear Power Plants: Quality Assurance”, Vienna (1974);
CNEN-NN-1.16: "QUALITY ASSURANCE FOR SAFETY OF NUCLEAR POWER PLANTS AND OTHER FACILITIES”
Code 50-C-QA (Rev. 1): “Code on the Safety of Nuclear Power Plants: Quality Assurance”, Vienna (1989);
CNEN-NE-1.21: “MAINTENANCE OF NUCLEAR POWER PLANTS”
Safety Guide 50-SG-07 (Rev. 1): “Maintenance of Nuclear Power
Plants”, Vienna (1990).
CNEN-NE-1.26: “SAFETY OF NUCLEAR POWER PLANTS OPERATION”
Code 50-C-O (Rev.1): “Code on the Safety of Nuclear Power Plants: Operation”, Vienna (1988).

8. CNEN-NE-1.27:“QUALITY ASSURANCE IN THE PROCUREMENT, DESIGN AND PRODUCTION OF FUEL ELEMENTS”
IAEA Reference Document:
Safety Guide 50-SG-QA11: "Quality Assurance in the Procurement, Design and Management of Nuclear Fuel Assemblies", Vienna (1983).
CNEN-NN-2.03: “FIRE PROTECTION IN NUCLEAR POWER PLANTS”
Safety Guide 50-SG-D2 (Rev. 1): “Fire Protection in Nuclear Power Plants”, Vienna (1992).
CNEN-NE-5.01: "TRANSPORT OF RADIOACTIVE MATERIALS”
Safety Series No 6[SS6]: “Safe Transport of Radioactive Materials", Vienna (1973).
CNEN-NE-5.02"TRANSPORT, RECEIVING, STORAGE AND HANDLING OF FUEL ELEMENTS OF NUCLEAR POWER PLANTS”
IAEA Reference Documents:
Code 50-C-QA (Rev. 1): “Code on the Safety of Nuclear Power Plants: Quality Assurance”, Vienna (1989);
Safety Guide 50-SG-QA11: "Quality Assurance in the Procurement, Design and Management of Nuclear Fuel Assemblies", Vienna (1983);
Safety Guide 50-SG-D10: “Fuel Handling and Storage System in Nuclear Power Plants”, Vienna (1984);
Safety Guide 50-SG-O10: “Core Management and Fuel Handling for Nuclear Power Plants”, Vienna (1985).

9. CNEN-NE-5.03: "TRANSPORT, RECEIVING, STORAGE AND HANDLING OF NUCLEAR ITEMS”
IAEA Reference Document:
Safety Guide 50-SG-QA4: "Quality Assurance During Site Construction of Nuclear Power Plants”, Vienna (1981).
CNEN-NE-6.02: "LICENCING OF RADIOACTIVE FACILITIES"
REGULATORY POSITION 6.02/001: “PRESENTATION OF REPORTS FOR LICENCING OF IRRADIATION FACILITES”
Safety Series No 102: Safety Series No 102 – Recommendations for the Safe Use and Regulation of Radiation Sources in Industry, Medicine, Research and Teaching.
” Vienna (1992).

10. 2. STANDARDS AND REGULATORY POSITIONS ISSUED IN 2005
2.1 Basic Standard
CNEN-NN-3.01: “BASIC GUIDANCES OF RADIOLOGICAL PROTECTION”
IAEA Reference Document:
Safety Series No 115 [BSS 115]: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996).
REGULATORY POSITION 3.01/001: “EXCLUSION, EXEMPTION AND CLEARANCE CRITERIA OF RADIOLOGICAL PROTECTION REQUIREMENTS”
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996).
REGULATORY POSITION 3.01/002: “PONDERATION FACTORS TO RADIOLOGICAL PROTECTION UNITS”
No IAEA Reference Documents for this case.
Used Intenational Reference Documents:
International Commission on Radiological Protection. “Recommendations of the International Commission on Radiological Protection”, ICRP Publication No. 60, Pergamon Press, Oxford and New York, International Commission on Radiation Units and Measurements, Quantities and Units in Radiation Protection Dosimetry, ICRU Report No. 51, Pergamon Press, Oxford and New York, 1993.

11. REGULATORY POSITION 3.01/003: “DOSE COEFFICIENT FOR INDIVIDUAL EXPOSED DUE TO OCCUPATION”
IAEA Reference Document:
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996).
REGULATORY POSITION 3.01/004: “DOSE RESTRICTION, OCCUPATIONAL REFERENCE LEVELS AND AREAS CLASSIFICATION”
Safety Guide RS-G-1.1: “Occupational Radiation Protection”, Vienna (1999).
REGULATORY POSITION 3.01/005: “CRITERIA FOR CALCULATION OF THE EFFECTIVE DOSES AS FROM THE INDIVIDUAL MONITORING”
IAEA Reference Document:
Safety Report Series: “Assessment of Radiation Doses from Intakes of Radionuclides by Workers”, Vienna (2004).
REGULATORY POSITION 3.01/006: “PROTECTIVE MEASURES AND INTERVENTION CRITERIA IN EMERGENCY SITUATIONS”
IAEA Reference Documents:
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996);
Safety Series No 109: “Intervention Criteria in a Nuclear or Radiation Emergency”, Vienna (1994);
Safety Series No 55: “Planning for Off-site Response to Radiation Accidents in Nuclear Facilities”, Vienna (1981);

12. Tecdoc - 953: “Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents”, Vienna (1997);
Tecdoc – 955: “Generic Assessment Procedures for Determining Protective Actions during a Reactor Accident”, Vienna (1997).
REGULATORY POSITION 3.01/007: “INTERVENTION AND ACTION LEVELS AGAINST CHRONIC EXPOSURE”
IAEA Reference Document:
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996).
REGULATORY POSITION 3.01/008: “ENVIRONMENT RADIOLOGICAL MONITORING PROGRAM"
IAEA Reference Documents:
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996);
Safety Reports Series No 19: “Generic Models for Use in Assessing the Impact of Discharges of Radioactive Substances to the Environment”, Vienna (2001);
Safety Guide 50-SG-G2: “Information to be Submitted in Support of Licensing Applications for NPP”, Vienna (1979);
Safety Guide WS-G-2.3: “Regulatory Control of Radioactive Discharges to the Environment”, Vienna (2000);

13. Safety Guide NS-G-2.7: “Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plant”, Vienna (2002);
Safety Guide NS-G-3.2: “Dispersion of Radioactive Material in Air and Water andConsideration of Population Distribution in Site Evaluation for Nuclear Power Plant”, Vienna (2002).
REGULATORY POSITION 3.01/09: MODEL TO PREPARE REPORTS ON ENVIRONMENT RADIOLOGICAL MONITORING PROGRAM
IAEA Reference Documents:
International Atomic Energy Agency, BSS-115, IAEA Safety Series No. 115, “International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources”, IAEA Safety Series No. 115, IAEA, Vienna, Austria, 1996.
International Atomic Energy Agency, SAFETY REPORTS SERIES No. 19, IAEA Safety Reports Series, “Generic Models for Use in Assessing the Impact of Discharges of Radioactive Substances to the Environment”, IAEA Safety Reports Series No. 19, IAEA, Vienna, Austria, 2001.
International Atomic Energy Agency, SAFETY GUIDE No. 50-SG-G2, IAEA Safety Series, “Information to be Submitted in Support of Licensing Applications for NPP”, IAEA Safety Guide No. 50-SG-G2, IAEA, Vienna, Austria, 1979.
International Atomic Energy Agency, SAFETY GUIDE No. WS-G-2.3, IAEA Safety Standards Series, “Regulatory Control of Radioactive Discharges to the Environment”, IAEA Safety Guide No. WS-G-2.3, IAEA Vienna, Austria,

14. International Atomic Energy Agency, SAFETY GUIDE No. NS-G-2
International Atomic Energy Agency, SAFETY GUIDE No. NS-G-2.7, IAEA Safety Standards Series, “Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plant”, IAEA Safety Guide No. NS-G-2.7, IAEA, Vienna, Austria, 2002.
International Atomic Energy Agency, SAFETY GUIDE No. NS-G-3.2, IAEA Safety Standards Series, “Dispersion of Radioactive Material in Air and Water and Consideration of Population Distribution in Site Evaluation for Nuclear Power Plant”, IAEA Safety Guide No. NS-G-3.2, IAEA, Vienna, Austria, 2002.
US National Regulatory Commission Reference Documents:
US National Regulatory Commission, REGULATORY GUIDE 4.1, USNRC “ Measuring and Report of Radioactivity in the Environs of NPP”, USNRC Regulatory Guide 4.1, Washington, DC, USA, 1973.
US National Regulatory Commission, Regulatory Guide 4.8, USNRC, “Environmental Technical Specification for NPP”, USNRC Regulatory Guide 4.8, Washington, DC, USA, 1975.
US National Regulatory Commission, REGULATORY GUIDE 4.15, USNRC, “Quality Assurance for Radiological Monitoring Programs (Normal Operations) – Effluent Streams and the Environment”, USNRC Regulatory Guides 4.15, rev. 1, Washington, DC, USA, 1979.
US National Regulatory Commission, NUREG-0475, USNRC “Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities”, USNRC NUREG-0475, Task Group Report, Washington, DC, USA, 1978.
US National Regulatory Commission, NUREG-1301, USNRC, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Control for PWR”, NUREG-1301, USNRC, Generic Letter 89-01, Supplement No 1, Washington, DC, USA, 1991.
ICRP:
International Commission on Radiological Protection ICRP 43, ICRP Publication 43, “ Principles of Monitoring for the Radiation Protection of the Population”, ICRP Publication 43, Pergamon Press Press, 1984

15. 2.2 Guides On Mining, Milling and Norm Field
REGULATORY POSITION 3.01/10: “DOSE LEVELS TO NOTIFY CNEN”
IAEA Reference Document:
Safety Series No 115: “International Basic Safety for Protection Against Ionizing Radiation and for the Safety of Radiation Sources”, Vienna (1996). Safety Report Series No 17: “Lessons Learned from Accidental Exposures in Radiotherapy”, Vienna (2000); Safety Guide RS-G-1.5: “Radiological Protection for Medical Exposure to Ionizing Radiation”, Vienna (2002).
2.2 Guides On Mining, Milling and Norm Field
CNEN – NE – 4.01 Standard: “Safety Requirements and Radiological Protection for Mineral Installations”
CNEN Reference Document: CNEN – NE – 1.13 E CNEN – NE
IAEA Reference Document: International Atomic Energy Agency, BSS-115, IAEA Safety Series No. 115, “International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources”, IAEA Safety Series No. 115, IAEA, Vienna, Austria, 1996.
International Reference Documents: Canadian Guidelines for the Managemnt of Naturally Occuring Radioactive Materialss [NORM] – Canadian NORM Working Group of the Federal Provincial Territorial Radiation Protection Committe, October 2000, first edition.

16. European Commission, Radiation Protection 112: Radiological Protection Principles Concerning the Natural radioactivity of Building materials; European Commission, Radiation Protection 122: Practical Use of the Concepts of Clearance and Exception, Part I and Part II.
Licensing Guide LG – 1032: Guidlines on the Assessment of Radiation Hazards to Members of the Public from Mining and Minerals Processing Facilities, Council for Nuclear Safety, South Africa
A regulatory guide [Regulatory Position 6.02/002, December 2004] was prepared for the decontamination of pipes from the Brazilian petroleum industry with radium. The decontaminating activities by the operator will be enforced by CNEN.
To be used guided by the CNEN Standards: CNEN – NE 6.02 and CNEN – NE – 6. 05
CNEN-NE-6.02: "LICENCING OF RADIOACTIVE FACILITIES“
Revision Status: Starting
IAEA Reference Document:
Basic IAEA Reference Document for Revision: International Basic Safety Standards for Protection Against Ionising Radiation and for the Safety of Radiation Sources [1996] – Safety Series No. 115.
Safety Series No 102 – Recommendations for the Safe Use and Regulation of Radiation Sources Industry, Medicine, Research and Teaching.
IAEA – TECDOC – 1344 – Categorization of Radioactive Sources.

17. 3. CNEN STANDARDS UNDER REVIEW AT THE MOMENT
CNEN-NE STANDARD: “TRANSPORT OF RADIOACTIVE MATERIALS”
IAEA Reference Document [old version]: Safety Series Number 6 [SS6].
IAEA Reference Document for Revision:
Safety Standards Series STR-1: "Regulations for the Safe Transport of Radioactive Materials", Vienna (1996).
CNEN-NE STANDARD: “ Waste Management in Radiative Instalations“
The Brazilian waste management regulation is in accordance with the IAEA Safety Standard 111 – f [Principles of Radiactive Waste Management]. A revew of this document is under way in order to improve the discharge limit [clearance limits] included in the regulation [which today is based on the 10 CFR – USA CODE] according to the IAEA document WS – G – 2.3 [Regulatory Control of Radioactive Discharges to the Environment]. There is already in Brazil a national system for the radioactive waste management control according to the Safety Series 111 – S - 1 from the IAEA.
Improvemennts in the area are being planned such as the creation of the safety assesment division that will be responsible for the safety assement of all near surface disposal facilities in Brazil, including those from mining and milling activities.
The near surface waste disposal draft regulation developed by the waste management division of CNEN was based on the IAEA documents WS-R-1 [Near Surface Disposal of Radioactive Waste] and WS-G-1.1 [Safety Assessment for Near Surface Disposal of Radioactive Waste].

18. CNEN-NE - 6.02 STANDARD : “Licensing Irradiative Installations”
Revision Status: Starting
Basic IAEA Reference Document for Revision: International Basic Safety Standards for Protection Against Ionising Radiation and for the Safety of Radiation Sources [1996] – Safety Series No. 115.
Safety Series No 102 – Recommendations for the Safe Use and Regulation of Radiation Sources Industry, Medicine, Research and Teaching.
IAEA – TECDOC – 1344 – Categorization of Radioactive Sources.
CNEN - NE-1.01 STANDARD : “Licensing Nuclear Reactors Operators”
Revision Status: In conclusion
IAEA Reference Documents for Revision:
IAEA – TECDOC – 1411
NRC Documents: NUREG 1021 – Operator Licensing Examination Standard for Power Reactor.
NUREG – 1122 – Revision 2 – Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors.
Document under Development:
GUIDE – CNEN – DRS – 000 – ILLICIT TRAFICKING OF NUCLEAR, RADIOACTIVE AND SENSITIVE GOODS
IAEA Reference Documents for Preparation of the guide:
IAEA – TECDOC – 1311
IAEA – TECDOC – 1312
IAEA – TECDOC

19. II REGULATORY HIGHLIGHTS IN 2005
GENERAL COORDINATION FOR NUCLEAR INSTALATIONS
To ensure the safety of the nuclear installations, all phases of the facility implementation must comply with the licensing regulations established by CNEN. The licensing process comprises the following stages: site approval, construction license, authorization for initial operation and authorization for permanent operation, which are applicable to power reactors, research and fuel cycle facilities as well. The General Coordination for Nuclear Installations is responsible for the licensing and control of nuclear power plants, U mining and milling, nuclear fuel cycle facilities, research reactors, personnel qualification (reactor operators and radiation protection officers) and participation in emergency planning and preparedness.
Main Brazilian nuclear installations:
ANGRA 1 – 626 MWe - PWR - USA Technology (in operation)
ANGRA 2 – 1245 Mwe - PWR - German Technology (in operation)
ANGRA 3 – (waiting government decision; ongoing licensing process)
5 Research Reactors (1 under construction)
Uranium Mining and Milling (in Caetité, South of the State of Bahia)
Enrichment (Pilot Plant); Fuel Pellet Fabrication Fuel Assembly Fabrication; Navy Research installations

20. In 2005, 35 regulatory inspections were performed in ANGRA 1 and 2 by headquarter´s staff, in addition to the resident inspection work which produces daily reports on the operational status of both units. In addition, inspections in research reactors (6) and fuel cycle facilities (73) have been performed and 7 new reactor operators licenses and 43 licenses renewls issued.
Current activities are focused in the Periodic Safety Review of Angra 1 (report evaluated by CNEN); Steam Generators replacement of Angra 1; Ageing Management of Angra 1; Authorization for Permanent Operation of Angra 2; Assessment of the Revised Site Report and PSAR of Angra 3; PSA and Safety Performance Indicators of Angra 1 and 2; and Research Reactor certification process.
Licensing activities in the fuel cycle facilities are currently focused on the safety assessment of U mining and milling facility at Caetité, the site report analysis of Santa Quiteria (a Phosphorous Uraniferous P- U District, in the central part of the State of Ceará) and the license extension of the uranium enrichment plant at Resende, in Rio de Janeiro.

21. ON THE COORDINATION OF RADIOACTIVITY FACILITIES
The Coordination of Radioactivity Facilities (CORAD) had important achievements in First of all, we can highlight the accomplishment of the institutional goals of licensing, inspection and control. We issued about 500 new authorizations, 50 construction licenses and nearly 3000 approved licenses of radioactive material import. In the inspection program we had about 400 facilities inspected. We can also mention the beginning of CNEN’s program of certification of new supervisors in the medical area which had 100 applicants and in the industrial area a 198 professionals were certified as operators and 43 as supervisors.
We should also mention the implementation of the interaction between that coordination and organizations whose attributions are complementary to CORAD’s, specially those from the Health Ministry. These two organizations have been working together increasing the level of operational security in the medical radioactive facilities. New actions are being implemented with the Customs Authorities in order to improve the control of import and export of radioactive sources aiming at the accomplishment of the requirements of the Code of Conduct on the Safety and Security of Radioactive Sources. Concerning that, we are in the final stage of evaluation of an administrative agreement on the control of import and export of radioactive sources with Canada.

22. In order to better assist the licensee, we are implementing the Management System at CORAD. In 2005 we completed the first stage of that program when we were able to identify all the process involved. That system will provide a higher control and speed in the process of the licensing of radioactive facilities. During this year eight new employees were hired so that we are now able to meet the increasing demand for new licenses for the operation of radioactive facilities.
Internationally, this Coordination has been working intensively in the project of the implementation of the American-Iberian Network Radiological Security with the American-Iberian Forum of Regulatory Agencies. CORAD has also been working with the Brazilian Justice Department and Foreign Relations Ministry in order to prevent the illegal traffic of radioactive material throughout the Mercosul countries.

23. A full-scale emergency exercise for the Angra Nuclear Power Plant, in Rio de Janeiro was conducted on October 06, Around 600 representatives from the Army, Navy, Air Force, Police, Fire Brigade and the Civil Defense (Federal, State and Local) were involved.
Control Point and Monitoring by Field Teams from CNEN and The Brazilian Army

24. These series of exercises started in 1996 and since then full-scale exercises have been carried out every two years in odd years, the even ones are devoted to partial exercises. The exercise was prepared by an advisory Committee for the Response Planning to a Nuclear Emergency in the Angra dos Reis Municipality (COPREN/AR), which is composed by representatives from organizations in charge of the management of the Nuclear Emergency Plan for the State of Rio de Janeiro. During the exercise 22 objectives were demonstrated and evaluated by a group of 30 evaluators. Simultaneous actions were conducted in the field and in four nuclear emergency management centres. These centres are located in Brasília (the Federal Centre), Rio de Janeiro (the State Centre) and Angra dos Reis (the Local Centre and the Joint Public Information Centre). Examples of field actions are the use of helicopters from the Brazilian Navy and the Air Force to transport additional resources from the State to the affected region and ships from the Brazilian Navy to simulated the evacuation of the islands inside the emergency planning zone. Local schools were used as congregate centres to receive volunteers as evacuees.

25. POÇOS DE CALDAS LABORATORY COORDINATION –COLAB/MG
IAEA Technical Cooperation Programs
The Laboratory of Poços de Caldas has participated in technical cooperation programs with the IAEA. Due to its appropriate analytical infrastructure and to the consolidated qualification of its technicians it has participated in IAEA programs of laboratorial intercomparisons exercices and proficiency tests in the determination of radio nuclides and heavy metals in different matrixes such as the determination of anthropogenic gamma emitting radio nuclides in mineral matrix, determination of radio and uranium isotopes in water samples and the determination of heavy metals at trace levels in lichen samples.
The participation in those programs is essential for the validation of recently developed and routine analytical methodologies regarding that some of those are being spread out to other laboratories around Brazil. Moreover, COLAB participates in an intercomparison exercise on the assessment of internal doses from incorporation monitoring data, in colaboration with the IDEAS Project and the IAEA.

26. In 2005, COLAB initiated its participation in the ALMERA NETWORK (Analytical Laboratories for Measuring Environmental Radioactivity), organized and managed by the IAEA (Seibersdorf Laboratories). This network was established in for the purpose of providing radio analytical support in case of accidental release of radionuclides to the environment.
In the near future, COLAB intends to submit to the IAEA a request for accrediting in the ITWG (Nuclear Smuggling International Technical Working Group). The objective is to insert its laboratories to provide nuclear forensic analysis in order to generate appropriate answers in cases involving illicit traffic of radioactive and nuclear materials.

27. ON WASTE MANAGEMENT
With respect to waste management, CNEN has enforced to the hospitals, universities and research centres to submit a waste management plan demonstrating that their instalations fulfils all the radiological and safe/security requirements regarding to waste managemnt acording to the IAEA standards found in the related the Safety Standard CNEN-NE-6.05, before starting operation. More than hundred waste managent plans have been submited and analised up to now.
CNEN is participating actively in the IAEA/ASAM project [Applications of the Safety Assessment Methodologies for Near Surface Disposal Facilities] via the Waste and Transport and Mineral Resources Divisions. The importance and relevance of this project is ilustrated by the the number of people attending the opening meeting and the number of countries involved. Brazil is actively participating in three main areas: Safety Reassessment Working Group, Disused Sealed Sources and Heterogeneous Waste Working Group and Mining and Minerals Processing Waste Working Group.

28. ENHANCEMENT OF THE SAFETY AND SECURITY CULTURE
In 2005, special attention was given to enhance the safety and security culture related to the use of nuclear and radioactive material in the Brazilian society via the following activities that were performed all over the country in several opportunities.
1 –Training on Physical Protection and Safety for the area professionals.
2 – Educational Material distribution to the general public.
3 – Joint activities with the Brazilian Federal Police and other Brazilian related authorities.
4 - Press releases, bulletins, public meetings, lectures, interviews to radio and TV, annual reports, site in the internet and regulatory publications were regularly organized, published and distributed as well as answers to inquiries from the parliament, labor unions, environmental authorities, the media and public in general were provided in an almost daily basis.

29. ON THE MANAGEMENT SYSTEM
Brazil has actively taken part, via comments or by directly participating at NUSSC/RASSC/TRASSC/WASSC in the development of the Safety Requirements and Safety Guides Drafts which make part of the IAEA Management System Structure.
  An Action Plan was conceived for a concomitant implementation to the approval and edition of the IAEA Safety Standards, including the following activities to be coordinated by CNEN, as the national regulatory body:
The creation of working groups for the development of a Management Model according to those Safety Standards;
The organization of a review team which, based on the management model developed, shall carry out self-assessments and consequent improvements of the actual Management Systems; and
Up to date the national normative structure concerning the quality systems, inserting the necessary normative upgrade, according to IAEA Safety Requirements and Safety Guides.

30. Thanks!