Comprehensive Training on Nuclear Decommissioning Procedures

Slide Note
Embed
Share

This training course, conducted by the Ghana Nuclear Regulatory Authority, focuses on the decommissioning process of nuclear facilities. The content covers definitions, strategies, IAEA standards, and management aspects related to decommissioning. Key topics include decommissioning processes, planning, conducting actions, completion, and management. Important aspects and actions towards achieving the approved end state and releasing facilities from regulatory controls are detailed.


Uploaded on Sep 22, 2024 | 0 Views


Download Presentation

Please find below an Image/Link to download the presentation.

The content on the website is provided AS IS for your information and personal use only. It may not be sold, licensed, or shared on other websites without obtaining consent from the author. Download presentation by click this link. If you encounter any issues during the download, it is possible that the publisher has removed the file from their server.

E N D

Presentation Transcript


  1. Basic Professional Training Course on Nuclear Safety Ghana Nuclear Regulatory Authority Accra, Ghana 7-18 May 18-29 June 2018 Module XVIII - Decommissioning Ferenc Adorjan Expert in nuclear safety (Hungary) ferencadorjan@gmail.com

  2. Lerning objectives After completing be able to: this Module, the trainee will 1. Define decommissioning. 2. List the aspects of decommissioning. 3. List the strategies for decommissioning. 4. State the main IAEA Standards relating to decommissioning. Module XVIII - Decommissioning Module XVIII - Decommissioning 2 2

  3. Contents 1. Decommissioning Process 2. Planning of Decommissioning 3. Conduct of Decommissioning 4. Completion of Decommissioning 5. Management Module XVIII - Decommissioning 3 3 3

  4. INTRODUCTION Decommissioning: administrative and technical actions taken to allow the removal of some or all of the regulatory controls from a facility. Module XVIII - Decommissioning 4

  5. INTRODUCTION Aspects of decommissioning typically include: Planning for decommissioning, Conducting decommissioning actions and Terminating the authorization. Aspects of decommissioning have to be considered throughout all five major stages of the lifetime of a nuclear facility (siting, construction, commissioning, operation and decommissioning). Module XVIII - Decommissioning 5

  6. INTRODUCTION Decommissioning actions Activities as described in the final decommissioning plan (decontamination, dismantlement, waste management and clean-up). Completed when the approved end state has been reached. End state - the release of the facility from regulatory control. Strategies for decommissioning: Immediate dismantling or Deferred dismantling or Entombment Module XVIII - Decommissioning 6

  7. IAEA Standards Decommissioning of Facilities, IAEA General Safety Requirements No. GSR Part 6 Requirements related to: Protection of people and protection of environment, Responsibilities associated with decommissioning, Management of decommissioning, Decommissioning strategy, Financing, Planning of decommissioning during the lifetime of the facility, Conduct of decommissioning actions and Completion of decommissioning actions. Module XVIII - Decommissioning 7

  8. IAEA Standards Safety Guides regarding the decommissioning of specific types of facility: SSG-47 Decommissioning of Nuclear Power Plants, Research Reactors and Other Nuclear Fuel Cycle Facilities (revision of WS- G-2.1 and 2.4); Decommissioning of Medical, Industrial and Research Facilities, IAEA Safety Guide WS-G-2.2 (1999. Under revision). General Safety Requirements and Guides also includes issues on decommissioning. Module XVIII - Decommissioning 8

  9. IAEA Standards Safety Guides addressing important aspects of decommissioning, that are of interest of all types of facilities are: Safety Assessment for the Decommissioning of Facilities Using Radioactive Material, IAEA Safety Standards Series No. WS-G-5.2; Release of Sites from Regulatory Control on Termination of Practices, IAEA Safety Standards Series No. WS-G-5.1; Application of the Concepts of Exclusion, Exemption and Clearance, IAEA Safety Standards Series No. RS-G-1.7. Module XVIII - Decommissioning 9

  10. DECOMMISSIONING PROCESS - Learning objectives 1.Describe the protection of people and the environment. 2.List the responsibilities of the government, the regulatory body, the licensee. 3.Describe the decommissioning option. 4.Define the immediate and deferred dismantling. 5.Describe the facilitating decommissioning. Module XVIII - Decommissioning 10

  11. DECOMMISSIONING PROCESS Time period of decommissioning stage may range from a few years to decades Nuclear installation or its remaining prats may also be considered decommissioned if incorporated into a new or existing facility Decommissioning of a nuclear installation on a multifacility site. Radiation protection of both workers and members of the public should be provided During decommissioning and further use of the site. Module XVIII - Decommissioning 11

  12. Protection of people and environment Graded approach used for all aspects of decommissioning in determining the scope and level of detail for any particular facility. In consistency with the magnitude of the possible radiation risks. The final decommissioning plan is supported by a safety assessment addressing the planned decommissioning actions and incidents that may occur or situations that may arise during decommissioning. Module XVIII - Decommissioning 12

  13. Responsibilities Nuclear facility taken out of service responsibility may be transferred to a different organization (recommended) Operating organization of the installation undergoing decommissioning is ultimately responsible for the safety. Responsibilities of the government To establish and maintain a governmental, legal and regulatory framework for all aspects of decommissioning. Module XVIII - Decommissioning 13

  14. Responsibilities Responsibilities of the regulatory body Authorise and oversight of decommissioning; Needs to establish safety requirements, adopt regulations and guides, including management of the resulting radioactive waste, and takes actions to ensure that the regulatory requirements are met. Responsibilities of the licensee Implements planning for decommissioning, carries out the decommissioning actions; The licensee is responsible for all aspects of safety, radiation and environmental protection during decommissioning. Module XVIII - Decommissioning 14

  15. Decommissioning strategy Immediate dismantling- removal of all radioactive materials from the site (allowing unrestricted release); Decommissioning actions begin shortly after the permanent shutdown. Equipment, structures, systems and components of a facility containing radioactive material are removed and/or decontaminated. Deferred dismantling - when dismantling is postponed; All or part of a facility containing radioactive material is either processed or placed in such a condition that it can be put in safe storage and the facility maintained until it is subsequently decontaminated and/or dismantled. Facility containing radioactive material is either processed or placed in such a condition that it can be put in safe storage. Module XVIII - Decommissioning 15

  16. Decommissioning strategy Selection of a normal decommissioning strategy is justified by the licensee (legislation, safety, resources, site use, etc). Licensee and Regulator should also consider: Sudden shutdown Decommissioning strategy reviewed to determine of revision of strategy is required. Shutdown caused by an accident Before approved decommissioning plan is implemented, facility needs to be brought to a safe configuration. Module XVIII - Decommissioning 16

  17. Decommissioning strategy Issues to be considered during the selection process Evaluation of various decommissioning options is performed with special emphasis on the balance between: Safety Available Resources* requirements *with regard decommissioning timeline . Module XVIII - Decommissioning 17

  18. Safety Radiological and non-radiological hazards are identified in a formal safety assessment; To provide appropriate protective measures to ensure safety of workers and the public and protection of the environment. Decommissioning may involve operations that may not be normal during the operation of the installation; Significance of non-radiological hazards may be increased, Problem of ageing of the reactor s components becomes important when deferred decommissioning is being considered. Safety assessment helps to ensure safety of the decommissioning process. Module XVIII - Decommissioning 18

  19. Financing Responsibilities in respect of financial provisions for decommissioning are set out in national legislation. To provide and ensure that adequate financial resources are available when needed to ensure safe decommissioning. All activities described in the decommissioning plan are included in the estimation of the cost for decommissioning. The cost estimate is updated on the basis of the periodic update of the initial or final decommissioning plan. Decommissioned facility is released with restrictions on its future use financial resources are available for monitoring, surveillance and control of the facility throughout the necessary time period. Module XVIII - Decommissioning 19

  20. Availability of existing expertise The availability and utilization of facility specific expertise is highly important for efficient and safe operations during decommissioning. Expertise could: Decrease the potential for events such as industrial accidents or overexposures and May help to reduce problems associated with loss of a corporate memory, and retraining or recruiting of new personnel. Module XVIII - Decommissioning 20

  21. Considerations relating to the public Issue of public concerns surrounding decommissioning is largely centred on the concern of waste disposal. Public opinion is also influenced by other factors like: Local factors, including the anticipated development and use of land after decommissioning; Local employment considerations after cessation of facility operation and during decommissioning; and Visual impact and the public attitude. Module XVIII - Decommissioning 21

  22. Facilitating decommissioning Requirements for decommissioning are considered: I. II. At the design stage for a new reactor installation or As soon as possible for existing installations. Considerations at the design and construction phase A baseline background radiological characterization of the site for the proposed facility and the facility itself need to be undertaken. Design features that need to be considered for decommissioning: Careful selection of materials and optimization of the facility s design, layout and access routes. Module XVIII - Decommissioning 22

  23. Facilitating decommissioning Considerations during facility operation Accurate and relevant records. Records are configured so that those relevant to decommissioning may be readily identified. In addition to drawings and diagrams, photographic records of the construction and operational phases of the reactor lifetime are kept. During operations, consideration is given to minimizing the extent of contamination of structures and surfaces, segregation of different categories of wastes, and avoidance and prompt clean-up of spillages and leaks. Module XVIII - Decommissioning 23

  24. PLANNING OF DECOMMISSIONING- Learning objectives 1. The planning of decommissioning. 2. The objectives and steps of a safety assessment. 3. The hazards during decommissioning. 4. The results of regulatory review of a safety assessment. Module XVIII - Decommissioning 24

  25. PLANNING OF DECOMMISSIONING A decommissioning planis prepared by licensee for each nuclear facility. The operating organization plans for adequate financial resources to ensure the decommissioning of a nuclear facility. Three stages of planning are envisaged: initial, ongoing and final; Degree of detail will increase from the initial to the final decommissioning plan. Information on type of safety related documents needed are provided in IAEA Safety Report Standard Format and Content for Safety Related Decommissioning Documents. Module XVIII - Decommissioning 25

  26. Initial planning of decommissioning Initial decommissioning plan is submitted with the application for authorization to operate the facility; To demonstrate the feasibility of decommissioning. Initial plan is updated as necessary with: Operational experience gained, Lessons learned from the decommissioning of similar facilities, New or revised safety requirements, or Technological developments relevant to the selected decommissioning strategy. Module XVIII - Decommissioning 26

  27. Final Planning of decommissioning Licensee informs regulatory body about planned shutdown, when time of the permanent shutdown of a facility is known. Prior to the conduct of decommissioning actions, a final decommissioning plan shall be approved by the regulatory body Updates of the final decommissioning plan include: Experience gained in decommissioning, New or revised safety requirements, or New or revised national regulations. Module XVIII - Decommissioning 27

  28. Safety assessment Objectives of safety assessment are: To support the selection of the decommissioning strategy, the development of a decommissioning plan and associated specific decommissioning activities; To demonstrate that exposures of workers and of the public are as low as reasonably achievable (ALARA) and do not exceed the relevant limits or constraints. Safety assessment: Forms an integral part of the decommissioning plan, Must be commensurate with the complexity and potential hazard of the installation, Need to be consistent with the decommissioning plan and with other relevant national and site specific strategies and requirements. Module XVIII - Decommissioning 28

  29. Safety assessment - General considerations In development and review of safety assessment graded approach is applied a process by which the level of analysis, the documentation and the actions necessary to comply with the safety requirements and criteria are commensurate with the following factors: Purpose and scope of the safety assessment; Uncertainty issues, radiological hazards and likelihood of hazards; Complexity, safety requirements and availability of applicable safety assessment. Module XVIII - Decommissioning 29

  30. Safety assessment content Description of the installations/facilities and of the decommissioning activities Description of the installations/facilities include: Site and local infrastructure dose and/or risk calculations, Installations/facilities safety functions and their associated SSCs, Inventory of radioactive material relevant radionuclides and calculated and measured activity; the radionuclide distribution and the dose rate distribution, Operational history operational records, post-operational on-site and off-sitesurveys and information from ongoing decommissioning activities. Module XVIII - Decommissioning 30

  31. Safety assessment - Hazards during decommissioning All relevant hazards to workers, public and the environment are included in decommissioning safety assessment: Radiation exposures, Toxic and other dangerous exposures, Industrial hazards. Initiating events includes those arising internally from the decommissioning activities, arising externally and human induced; Initiating event meaning an identified event that leads to anticipated operational occurrences or accident conditions and that challenges safety functions. Module XVIII - Decommissioning 31

  32. Safety assessment - Defence-in-depth Defence-in-depth principle used to: Prevent escalation of anticipated operational occurrences and Maintain effectiveness of physical barriers. This include: Operational limits, controls and conditions to prevent adverse consequences; Protective measures which ensure that any accidents will not result in significant harm to workers, the public or the environment; and Mitigate the consequences of accidents that could occur. Module XVIII - Decommissioning 32

  33. Safety assessment - Safety functions Safety functions should not be compromised during decommissioning: Control of reactivity, Cooling of radioactive material, Confinement of radioactive material, Shielding, Radiation detection and actuation of alarms, Fire suppression and ventilation. Module XVIII - Decommissioning 33

  34. Safety assessment - Long term safety Decommissioning should not not impose unacceptable hazards or undue burdens on future generations. For deferred dismantling safety assessment demonstrate that installation/facilities will: Meet relevant safety requirements and criteria in dismantling period and Can be safely decommissioned in future. Module XVIII - Decommissioning 34

  35. Safety assessment managing of Uncertainties All known uncertainties should be taken into account; Quality, reliability and availability of information from the characterization of the installations/facilities may be limited; Clean-up activities may not be well defined; and Scenarios and the stages in the decommissioning plan may need to be revised on the basis of knowledge gained from previous stages in the process or from other similar activities at other facilities or sites. Where uncertainties are significant, the safety assessment considers applying a phased approach to the safety assessment for decommissioning. Addressing individual phases and/or stages of the decommissioning plan so as to reduce the uncertainties as decommissioning progresses. Module XVIII - Decommissioning 35

  36. Safety assessment Results of safety assessments demonstrate compliance with regulatory requirements and criteria expressed in terms of effective dose or in terms of risk. Safety measures (engineered and procedural) must be commensurate with the likelihood of the occurrence of accidents and their possible radiological consequences. Module XVIII - Decommissioning 36

  37. Regulatory review of the safety assessment The principal objectives of regulatory reviews of safety assessment are: To consider whether the safety assessment provides an appropriate basis to support the proposed decommissioning strategy, plan and activities; To support the authorization process for the decommissioning strategy, plan and activities by confirming that all relevant safety requirements and criteria have been met; To identify any regulatory limits and conditions that will need to be applied during decommissioning or before decommissioning activities may be commenced; and To provide an input into the process of releasing the site from regulatory control. Module XVIII - Decommissioning 37

  38. Regulatory review of the safety assessment The results of the review of the safety assessment demonstrate: The safety assessment is consistent with the decommissioning plan and other related safety assessments; Decommissioning activities are optimized with due regard to dose and risk constraints for planned activities; Suitable and sufficient safety measures (procedural measures and engineered safety features) will be in place so that the decommissioning activities can be carried out safely and in accordance with all relevant safety requirements and criteria, and in an optimized manner; Surveillance measures and maintenance measures are adequate to ensure safety; Emergency planning and preparedness during decommissioning are adequate; and Good engineering practice has been used in developing the proposals for decommissioning. Module XVIII - Decommissioning 38

  39. CONDUCT OF DECOMMISSIONING - Learning objectives 1. Critical tasks of decommissioning. 2.State the concerns with fuel removal. 3.The importance of containment regarding the decommissioning. 4.The decontamination. 5.The final radiological survey. Module XVIII - Decommissioning 39

  40. CONDUCT OF DECOMMISSIONING The licensee shall implement the final decommissioning plan, including management of radioactive waste, in compliance with national regulations. Decommissioning techniques shall be selected such that: Protection of workers, the public and the environment are optimized, Generation of waste is minimized, and Potential negative impact on storage and disposal of waste is minimized. As decommissioning actions progress (decontamination, cutting and handling of large components) new hazards may arise. Impact of these actions on safety shall be assessed and managed. Module XVIII - Decommissioning 40

  41. Critical tasks of decommissioning Initial characterization of decommissioning Survey of radiological an non-radiological hazards: Important input for safety assessment, Input for implementing a safe approach during the work, Conducted to identify the inventory and location of radioactive and other hazardous materials. Radiation and contamination maps are prepared with adequate number of radiation and contamination surveys. Inventory of all hazardous chemicals present in the installation should be conducted. Module XVIII - Decommissioning 41

  42. Critical tasks of decommissioning Fuel removal from reactors Fuel should be removed prior to conduct of decommissioning actions; Spent fuel removal from reactor at the end of its operational lifetime is part of operation. Procedures for the removal, storage and shipment of fuel are the same as those used during normal operation. On-site interim storage facilities for spent fuel care is taken with respect to possible interference with future decommissioning activities at the reactor installation. Module XVIII - Decommissioning 42

  43. Critical tasks of decommissioning Containment maintenance and modification Containment systems should be retain as long as necessary and feasible; Containment is important element of defence-in-depth to prevent the movement of residual radionuclides. Adequate containment is planned and demonstrated when the airborne contamination may be raised: Containment related barriers or devices are removed or altered, Cutting and dismantling operations are carried out. Module XVIII - Decommissioning 43

  44. Critical tasks of decommissioning Decontamination Decontamination are activities directed to the removal or reduction of radioactive contamination. Decontamination may be applied to: Internal or external surfaces of components and systems, Structural surfaces, and Tools employed in decommissioning. Decontamination can be conducted before, during or after dismantling. Module XVIII - Decommissioning 44

  45. Critical tasks of decommissioning Decontamination The objectives of decontamination include: Reduction of exposures during decommissioning activities; Minimization of the volume of the categories of material to be classified or disposed of as solid radioactive waste; and Increase of the possibility of recycle and reuse of equipment, materials or premises. Important to exchange information and experience; Especially for smaller facilities, where development of new and optimised techniques is less feasible. Module XVIII - Decommissioning 45

  46. Critical tasks of decommissioning Dismantling Special tools and devices may be needed during dismantling tools and devices should be tested before their use. Considerations for determining most effective and safe dismantling: Equipment is simple to operate, decontaminate and maintain; Effective methods for controlling airborne radionuclides implemented; Effective control of discharges to the environment; Underwater dismantling and cutting water processing to ensure good visibility and assist in effluent treatment; Effect of each task on adjacent systems and structures are evaluated; Waste containers, handling systems and routes are defined in advance. Module XVIII - Decommissioning 46

  47. Critical tasks of decommissioning Final radiological survey Survey of the residual radionuclides at the facility site must be performed after completion of decommissioning; To demonstrate that the residual activity complies with the criteria set by the national regulatory authority and the decommissioning objectives have been fulfilled. Final survey report includes: Criteria used; Methods and procedures to ensure that the criteria were met; and Measurement data, including appropriate statistical analysis and systematic approaches used. Module XVIII - Decommissioning 47

  48. Additional aspects of decommissioning actions Radiation protection The radiation protection programme ensures that radiation protection is optimized and that doses are kept within appropriate limits. During decommissioning special situations may need to be considered, which may require: Use of specialized equipment and Implementation of certain non-routine procedures. Module XVIII - Decommissioning 48

  49. Additional aspects of decommissioning actions Radiation protection The radiation protection programme should be clearly set out in the decommissioning plan. Involved in its execution properly trained and have access to appropriate equipment for carrying out radiation surveys. Decommissioning work should be planned and carried out using work order procedures and radiation work permits, with adequate involvement of radiation protection expertise. Module XVIII - Decommissioning 49

  50. Additional aspects of decommissioning actions Material management Material management is considered in the decommissioning plan and the safety assessment to ensure radiological protection. Radiological consequences are assessed from: The management of material arising from decommissioning, including metal, building rubble, liquids and other material destined for release from regulatory control; and The management of radioactive waste on the site, including any processing, handling and storage of the waste. The safety assessment for decommissioning need to be consistent with relevant site and national strategies and regulatory requirements for the management of material and radioactive waste. Module XVIII - Decommissioning 50

Related


More Related Content