DS450 Decommissioning GSR Part 6 revised 19Mar2013 ... - gnssn

More documents

Recommendations

Info

1.19. This publication does not address the remediation of areas contaminated by residualradioactive material arising from past activities that (1) were never subject to regulatory control or (2)were subject to regulatory control but not in accordance with the requirements of the existing IAEAand national safety standards. It also does not address the remediation of areas affected by a nuclear orradiological emergency, after an emergency has been declared to be over. However, most of therequirements established in this safety standard can also be applied to decommissioning after anincident has occurred or a situation has arisen that has resulted in serious damage to, or thecontamination of, a facility, or simply after a premature shutdown. The requirements for theremediation of such areas are established in Ref. [4].1.20. The management of fresh nuclear fuel, spent nuclear fuel and radioactive waste generatedduring operations is not usually considered part of decommissioning. It is addressed as part ofoperations and is outside the scope of this publication.1.21. This publication addresses the radiological hazards resulting from decommissioning. Nonradiologicalhazards, such as industrial hazards or hazards due to chemical waste, can be significantduring decommissioning. Such hazards require due consideration in the planning and implementationprocess, in the safety assessments and environmental assessments, and in the estimation of costs andthe provision of financial resources for the decommissioning project. However, these issues areoutside of the scope of this publication and are not explicitly addressed here.1.22. Security aspects have to be considered during decommissioning, but are out of the scope ofthis publication. The IAEA issues recommendations on nuclear security in the IAEA Nuclear SecuritySeries [5].STRUCTURE1.23. Section 2 establishes the requirements for the protection and safety of workers and the publicand for the protection of the environment. The responsibilities of the major parties associated withdecommissioning are discussed in Section 3. Section 4 establishes the requirements for themanagement of decommissioning and Section 5 establishes the requirements for selecting adecommissioning strategy. Section 6 establishes the requirements for the financing ofdecommissioning and Section 7 discusses the planning for decommissioning that is done during thefacility’s lifetime. Section 8 establishes the requirements to be followed when conductingdecommissioning actions. Section 9 establishes the requirements for determining whendecommissioning has been completed, including surveys to demonstrate the completion ofdecommissioning actions and the termination of authorization.
2. PROTECTION OF PEOPLE AND PROTECTION OF THE ENVIRONMENTRequirement 1: Optimization of protection and safetyExposure during decommissioning shall be considered to be planned exposure situation and therelevant requirements of the Basic Safety Standards shall be applied accordingly duringdecommissioning.2.1. The relevant dose limits for the exposure of workers and members of the public shall beapplied during decommissioning [4]. Radiation protection of persons who are exposed as a result ofdecommissioning actions shall be optimized with due regard to the relevant dose constraints.2.2. In addition to provisions to protect against exposure during planned activities, provision shallbe made during decommissioning for protection against, and for mitigation of, exposure due to anincident. However, if the incident or the particular situation is of such a nature as to warrantremediation, the IAEA requirements from the Ref. [4] apply.2.3. Compliance with national environmental protection regulations and requirements of the BSS[4] addressing protection of the environment shall be maintained during decommissioning and beyondif a facility is released with restrictions on future use.Requirement 2: Graded approachA graded approach shall be used for all aspects of decommissioning in determining the scopeand level of detail for any particular facility, consistent with the magnitude of the possibleradiation risks arising from the decommissioning.2.4. The type of information and the level of detail in the decommissioning plans and supportingplanning documents, including safety assessment, shall be commensurate with the type, scale,complexity, status and stage in the lifetime of the facility and with the hazards associated with thedecommissioning of the facility [4, 6].2.5. Conducting decommissioning by the licensee and the regulatory oversight shall becommensurate with the magnitude of hazards and risks (e. g. Safety Assessment, Emergency ResponseArrangements).5
Page 1: Date: 14 March 2013IAEA SAFETY STAN
Page 6 and 7: 1.6. Planning for decommissioning b
Page 10 and 11: Requirement 3: Assessment of safety
Page 12 and 13: authorization or licence conditions
Page 14 and 15: 4.2. An integrated system for the m
Page 16 and 17: 7. THE PLANNING OF DECOMMISSIONING
Page 18 and 19: 7.13 If the final decommissioning p
Page 20 and 21: transport regulations [11]. In case
Page 22 and 23: REFERENCES[1] EUROPEAN ATOMIC ENERG

DS450 Decommissioning GSR Part 6 revised 19Mar2013 ... - gnssn

Create successful ePaper yourself

Delete template?

Save as template?