Prof. Dr. Farouk M. A. Rahman

�Legal

� Decree of the president of the United Arab Republic , law 59 of 1960 on the regulation of work with ionized radiation and protection against its dangers

� Atomic Energy Act and its enforcement decree and regulations No.288, year 1957

�Legal (2)

� Law No. 4 for year 1994 (Law of the Environment) ,

� Prim Minister’s Decree No. 338 for year 1995 for (the Executive Regulations for the Law of Environment No. 4) ,

� According to that Law, a license is required for handling the radioactive materials including � collecting,

� transporting,

� storing,

� treating,

� and using the radioactive materials.

� Law No.4 strictly stipulates to get the license from NCNSRC-AEA

� Decree of The President of Egypt No 125, year 2006 for the Egyptian System for implementing safeguards over Egyptian Nuclear activities

�Legal (3)� Law No. 7 for year 2010 (Law of regulating nuclear and

radiation activities)

� The law moves the Egyptian nuclear regulatory framework closer to be in agreement with international safety standards.

� Under the law, the regulatory powers transferred to a separate and independent regulatory body (Nuclear and Radiation Control Authority, NRCA).

� All nuclear and Radiation activities and nuclear and Radiation facilities in Egypt will be regulated by the new body.

� The law regulates the decommissioning of nuclear facilities

� The law has legal arrangement for a financing mechanism covering decommissioning

�Legal (4)

The Legal system in Egypt cover all aspects for non radioactive materials parts of decommissioning

Minister of Electricity and

Energy

Technical assistance office for licensing of sealed sources

Nuclear Power plants (NPP)

Atomic Energy Authority

Egyptian Legal FrameworkBefore the law No.7,2010

Prime Minister

Ministry ofhealth

National Centre for Nuclear Safety and Radiation Control (NCNSRC)

(Regulatory Body of Egypt)

Minister of Electricity and

Energy

Nuclear Power plants (NPP)Atomic Energy Authority

Egyptian Legal Frameworkafter the law No.7,2010

Nuclear and Radiation Control Authority

NRCA

Prime Minister

Ministry ofhealth

Technical assistance office for licensing of sealed sources

� The Egyptian Atomic Energy Authority (AEA)

was Established in 1955.

� The AEA before 2010 is the Operator of both

�the Egyptian Nuclear Facilities

�and the National Nuclear Regulation

At that time, the Minister of Electricity and Energy has created an internal regulatory system that provides separation and independence between:

•the operating (AEA)• and regulating body (NCNSRC), •and requires the Egyptian nuclear facilities and activities to be licensed by NCNSRC

� The AEA is organized into three

research and one regulatory centers

�1. The Nuclear Research Centre

(NRC)

�2. The Hot Laboratories and Waste

Management centre (HLWMC)

Both Centers are located in Inshas

� The AEA is organized into three research and

one regulatory centers

� 3. The National Centre for Radiation Research

and Technology (NCRRT)

� 4. The National Centre for Nuclear Safety and

Radiation Control (NCNSRC)

Both Centers are located in Nasr City eastern of

Cairo.

Atomic Energy Authority

PRESIDENT Board of Directors

ET-RR-2 Project Cyclotron Project

Nuclear Research Centre (NRC)ET-RR-1 Reactor

Hot Laboratories and Waste Management centre (HLWMC)

Vice President

(Research Projects)

National Centre for Radiation Research and Technology (NCRRT)

Security

General secretariat Admin. And Finance

Vice President( Training & International Cooperation)

Technically Independent

1- Research Reactors (ET-RR-1 & ET-RR-2)

- Reactor Operators - Fuel Fabrication Factory for ET-RR-2

2- Nuclear Power plant - Reactor Operators - Fuel Fabrication Factory

3- Accelerators ( Cyclotron & Linear Accelerator ) - Industrial Irradiator ( Egypt’s’ Mega Gamma I & II).

4 - Applications of radioisotopes in Industry, Medicine, Agriculture and Research all over Egypt

- Laboratories, Factories (60) and Hospitals (600) using Radioisotopes all over Egypt

- Radioisotopes Production- Any other radiation activities

5 - Radioactive Waste Disposal Facility- Radioactive Waste Treatment Plant

6- Transportation of Radioactive Materials all over Egypt

The ( ET – RR – 1) Facility :- commissioned in 1961

� The (ET-RR-1), is a tank-type which was purchased from the former USSR, on the basis of a bilateral agreement . The fuel is 10% enriched uranium and the coolant, moderator and reflector are ordinary distilled water.

� The normal power of 2 MW corresponds to an average thermal neutron flux of 1013n /cm2S.

� It contains 8 vertical channels for material irradiation, 9 horizontal beam tubes for neutron experiments ,one thermal column ,four hot cells and two spent fuel storage .

� • Decommissioning

A preliminary decommissioning plan is available for ETRR-1 (initial planning & ongoing planning) see Appendix B

The ( ET – RR – 2) Facility :-

� The (ET-RR-2 ) is of the open pool type, 22 MW Power, cooled and moderated by light water , with Beryllium reflectors

� The nominal power of 22 MW and a maximum thermal neutron flux of 2.7x1014 n/ cm2 s

� It is used for research in neutron physics, materials science, Nuclear fuel R&D ;

� radioisotope production, neutron radiography, activation analysis, boron neutron capture therapy and training in nuclear engineering and reactor operation.

� • Decommissioning

A preliminary decommissioning plan is available for ETRR-2 (initial planning & ongoing planning) see Appendix A

L.1 Egypt have independent Regulatory Body, by law No 7,2010

L.2 Egypt has not developed a complete set of regulatory documents governing decommissioning activities covering all regulatory functions.

L.3 Egypt have legal arrangement for

a financing mechanism covering

decommissioning.

L.4 Egypt has clear Legal Framework

for implementing safeguards over

Nuclear activities including

decommissioning .

L.5 Legal responsibility for

implementing physical protection

and security arrangements for

decommissioning activities are clear.

L.6 Legal responsibility of the

operator of Et-RR-1 and ET-RR-2 for

decommissioning are clear.

L.7 The Legal system in Egypt cover all aspects for non radioactive materials parts of decommissioning of nuclear facilities.

Fuel Removal Authorization

(from site)

Waste Storage Decommissioning License

�Plan for Constructing a fuel storage building

�Transportation procedures

�Criticality calculation

�Safety & Security

�Site

�QA Procedures

�Monitoring plan

�Type and Capacity

�Facility layout and access

�Potential hazards

�Waste characterization

�Safety, Security &Safeguards

�Engineering structure

�Decommissioning Plan

�Decommissioning Management

�Decommission Method / Strategy

�Quality Assurance

�Financial Assurance

�Waste Management

�Responsibilities of Various Parties: Operator, Contractor, Other relevant parties.

�Estimation of :

–Time

–Dose

–Cost

�Future plan of the Site

Fuel Removal Authorization

Waste Storage Decommissioning License

The NRCA shall provide :

-Set of licensing guidance and procedures

-Competent personnel for reviewing the application;

�Acceptance criteria for fuel transportation and storage authorization

� licensing conditions.

The NRCA shall provide :

�Set of licensing guidance and procedures ;

�Competent personnel for reviewing the application;

�Acceptance criteria for waste storage license

� licensing conditions.

The NRCA shall provide :

�Set of licensing guidance and procedures ;

�Competent personnel for reviewing the application;

�Acceptance criteria for decommissioning license.

� licensing conditions,

The structure of the Decommissioning Plan will be in accordance of

the IAEA decommissioning documentation (Safety Reports Series

No. 45):

� 1. Introduction: done

� 2. Facility description: Physical description of the site and

facility; operational history; radiological status of systems and

equipment; radioactive and toxic material inventory (partially

done)

� 3. Decommissioning strategy: Objectives; decommissioning

alternatives; financial arrangements; selection and justification

of preferred option (to be done)

� 4. Project management: resources; organization and

responsibilities; review and monitoring arrangements; training

and qualifications; reporting and records (to be done)

The structure of the Decommissioning Plan will be in accordance of

the IAEA decommissioning documentation (Safety Reports Series

No. 45):

� 5. Decommissioning activities: Description and schedule of phases

and tasks; decontamination activities; dismantling; waste

management; surveillance and maintenance programs (to be

done)

� 6. Cost Estimate and Funding:

Coast estimate is based on the timing of dismantling. The ETRR-2

is one research institute of Egyptian Atomic Energy Authority

(EAEA), and then the decommissioning costs will be provided by

EAEA. Funds for the ETRR-2 decommissioning will be provided by

the Government.

The structure of the Decommissioning Plan will be in accordance of

the IAEA decommissioning documentation (Safety Reports Series

No. 45):

� 7. Safety assessment: dose predictions for tasks; demonstration

of ALARA for tasks; radiation monitoring and protection system;

physical security and materials control; management of safety;

risk analysis; operating rules and instructions; justification of

safety for workers, general population, and environment ( to be

done)

� 8. Environmental impact assessment: Background data;

Description of project; Environmental protection programme;

Effluent monitoring programme; Effluent control programme (to

be done)

The structure of the Decommissioning Plan will be in accordance of the IAEA

decommissioning documentation (Safety Reports Series No. 45):

� 9. Quality assurance program: (partially done in application of

the existing procedures)

� The quality assurance (QA) programme to be applied during decommissioning may be

described in a separate document referenced and summarized in the decommissioning plan.

The document in place during the facility operation is generally valid for the decommissioning

activities, except for revisions to the organizational structure and other minor changes. The QA

topics that have to be elaborated are described below

� Organization

� Organizational chart, duties, responsibilities, lines of communication and reporting to be

included

� Training programme

� Document control

� Control of measuring and test equipment

� Corrective actions

� QA records

� Audits and surveillance

� Lessons learned

The structure of the Decommissioning Plan will be in accordance of the IAEA

decommissioning documentation (Safety Reports Series No. 45):

� 10. Radiation protection and safety program: (partially done)

� The radiation protection program for decommissioning should include

appropriate procedures for:

� Personnel control.

� Application of the optimization principle and assessment of estimate for doses

during specific tasks.

� Appropriate monitoring on and off site

� Decontamination of personnel, equipment and structures

� Appropriate radiation monitoring of components and materials during their

disassembly, packing, transportation and storage.

� Environmental radiological surveillance

� Detecting and recording releases of radioactive material

� Recording the inventory of radiation sources

� Providing adequate training in radiation protection practices.

� 11. Final radiation survey and radiological clearance criteria: to

be done and exemption levels to be established.

The Decommissioning is in accordance with the IAEA Safety Reports Series No. 45

� 1. Introduction:

� 2. Facility description: (done)

� Site location and description

� Building and system description

� Facility operating history

� 3. Decommissioning strategy (undergoing)

� Decommissioning alternatives to select the preferred option (power upgrade or ….)

4. Project management: (to be done)

� Legal and regulatory requirements

� Project management approach

� Project and task management organization and responsibilities

� Safety culture

� Training and qualifications

� Schedules

� 5. Decommissioning activities: (to be done)

� 6. Cost Estimates and Funding:

� Coast estimate is based on time of dismantling. The ETRR-1 research

reactor belongs to the Egyptian Atomic Energy Authority (EAEA), which is

one of the governmental institutions. Funds for the ETRR-1

decommissioning will be provided by the Government.

7. Safety assessment: (to be done)

� Identification of waste streams

� Solid and Liquid radioactive waste

9. Safety assessment: (partially done)

10 Environmental assessment (to be done)

12.Quality assurance program: (partially done)

� in application of the existing SAR)

13 Emergency Plane (done)

14 Physical Security and Safeguards (done)

15 Final Radiation Survey (to be done)