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Necsa Project Approval Process IAEA

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Necsa Project Approval Process IAEA Powered By Docstoc
					  INTRODUCTION TO THE NECSA
PROJECT APPROVAL PROCESS AND
 LICENSING OF DECOMMISIONING
          PROJECTS

         Licensing Department




                                2010-08-12
  Necsa’s Project Approval Process- Contents



 Safety Case
 Project Approval Process
    Project Categorization
    SHEQ-INS-0800 process
    Safety Case compliance and verification
    Project Approval
 Example of a Safety Case for Decommissioning
Project Safety Case Structure
          heq
          Project Approval Process

Project Initiation



     Project         2,3    INS-0800 Process
  Categorization

              1
Internal Change            SHEQ Approval
Management                 Requirements
Process                    (Safety Case)


SHEQ Approval                                      SHEQ Approval
Requirements                                       recommendation
integrated into              Compliance        Y   to SC or
                             Verification
project                                            Authorized
management                                         individual as per
plan                                    N          project cat
                           Correction
                      Project Categorization
          Categorization Element                              Criteria

1   Installation                                 Existing or New?
2          Nuclear/Facility Safety               Change/Modification of IROFs or
                                                 SC-SSC
           Legislative Approval                  Change of Safety Envelope
3

4   SHE Inventories – (Materials and Waste)      Increase of material inventories/
                                                 new waste stream
           Operating procedures, facility        Extend of change required
5          arrangements and actions (including
           maintenance)

6   Security                                     Increase of Security Threat

    Safeguards                                   Modification of existing SG
7
                                                 requirements
                    INS-0800 Process

• Meeting between Licensing Department , Project Management
  Team and Discipline Specialists
• Utilization of checklist to identify project and phase specific safety
  case requirements
• Identification of hold points
• Acceptance and approval of Safety Case requirements by
  stakeholders
• Incorporation of Safety Case and SHEQ approval requirements into
  an integrated project plan
Project Approval
  Safety Case for the Decommissioning of a
             Conversion Plant
• Project Management
   –   Project Definition, Scope and Objectives
   –   Project Description, Organisation and Plan
   –   Project QA plan
   –   Work Planning and Schedule
• Project Evaluation
   –   PEIS
   –   Safety analyses of planned activities
   –   Safety assessment
   –   HIRA
  Safety Case for the Decommissioning of a
             Conversion Plant
• Plans and Programmes
   –   Plans to ensure compliance to Construction Regulations
   –   Work procedures, work planning and training
   –   OTS, ISI &MP applicable during decommissioning
   –   Waste Management Plan
   –   Environmental Monitoring Plan
   –   Statutory Equipment Management Plan
   –   Building Security and Emergency Plans
   –   RP Programme
   –   Medical Surveillance and OH programme
   –   Plan to handle asbestos
   –   Commissioning and Readiness
  Safety Case for the Decommissioning of a
             Conversion Plant

• External Approval
   – Public information
   – Regulatory approval
          Safety Assessment- Contents

 Purpose of the assessment of decommissioning activities
 Difference between safety assessment of decommissioning
  activities and other planned activities.
 General Assumptions
 Specific Assumptions and variables
 Activity specific dose calculations
             Purpose of Safety Assessment

• Ensure that safety is integrated in the development of
  decommissioning activities and plans(e.g. Sequence of activities)
• Optimization of protection (ALARA)
• Quantification of operator and public exposure levels in order to:
    – Demonstrate compliance with safety criteria
    – Identify appropriate project specific Technical Specifications, Operating Rules
      and Safety (including RP) related control measures
        Difference ico. Decommissioning ?

• Inventory effectively removed during shutdown
• Residual radiological conditions known- measurable/
  characterization
• Decommissioning activities well defined per section/task
• Consequence of specific decommissioning activities within
  characterised sections can be calculated for specific tasks with the
  application of simple models
• Emphasis on deterministic hazard assessment rather than on PRA
• Only limited engineering analyses
                 General Assumptions

• Conservatism- unless inherent constraints are high –justification of
  more realistic assumptions
• Exposure due to prevailing ambient radiological conditions as well
  as radiological conditions caused by specific decommissioning
  activities
• Limited credit taken for PPE.
• Annual exposure calculated as default
• Exposure via all exposure pathways are considered but could be
  eliminated based on relative contribution
         Specific Assumptions & Variables

• Radiological characteristics of sections/zones
    – Prevailing external dose rate- at various distances
    – Material at risk
       • Nuclide Composition
       • Physical Form e.g. Dry powder as surface contamination or in bulk
          form, AMAD
       • Chemical Properties e.g. Solubility (Class)
       • Quantities, Concentration and prevailing levels
    – Anticipated source term per decommissioning activity and AOO
        Specific Assumptions & Variables

• Planned decommissioning activities per section /zone
   – Main activities per section/zone required for scope of decommissioning
   – Anticipated duration of main activities
   – Anticipated change of radiological conditions as decommissioning
     advance
• Worker Interface
   – Main Worker categories per main activity defined per section/zone
   – Anticipated exposure parameters applicable per Workerr category per
     main task per section/zone
• Public Interface
Deterministic Hazard Assessment




                                  18
              Dose Calculation Methodology

• Inhalation Dose due to surface contamination

• Secondary Ingestion Dose due to surface Contamination




                                                          19
      Inhalation Dose due to surface contamination

Dh =(C)(Rs)(Fh)(I)(t)(Eh)     (Equation II.1, Annexure II, IAEA Safety Series No. 111-P-1.1)

where:

Dh = Committed effective dose in Sv a-1

C = Average surface contamination level in Bq/m2

Rs = Resuspension factor in m-1

Fh = Inhalation transfer factor for surface activity

I   = Inhalation rate in m3/h ( specified as 1.2 m3/h when doing light work, ICRP 23)

t   = Time in hours/a

Eh = Committed effective dose per unit intake via inhalation, in Sv/Bq




                                                                                        20
          Secondary ingestion dose due to surface
                      Contamination

Dg = (C)(Rg)(t)(Eg) (Equation II.2 in IAEA Safety Series No. 111-P-1.1, but for surface
    contamination)

where:

Dg = Committed effective dose, in Sv a-1

C = Average surface contamination level in Bq/m2

Rg = Secondary ingestion rate in m2/h

t   = Time in hours/a

Eg = Committed effective dose per unit intake via ingestion, in Sv/Bq




                                                                                          21
                                    Effective Dose

•   In order to calculate the Effective dose of a specific activity it is necessary to calculate
    besides the committed effective dose, also the external Dose component which could
    include:
      – Whole body Gamma dose
      – Skin dose
      – Dose to the lens of the eye
•   The Effective dose is the summation of all Dose components


       E=Wt.Ht




                                                                                              22
                                  ?



Methodology for assessing Internal dose due to volume contaminated
  material?




                                                                     23
Thank You!!!

				
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