Appendix CRF - Part 3 - Northamptonshire County Council

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The approach drives the correct behaviour down to the consignor in respect of the waste hierarchy because the approach enables remaining nuclide capacity (hence price) to be directly related to the environmental risk of that nuclide. The approach addresses the optimisation principle because the remaining capacity of the landfill is continuously optimised in a manner that ensures the overall risk guidance levels are not exceeded and the model will enable the operator and regulator to make informed choices. The capacity of the landfill is administered in a manner that ensures dose limits and constraints will not be exceeded with a significant safety factor to account for uncertainties. The approach maintains flexibility to account for the uncertain overall inventory of decommissioning wastes to be produced as required by regulatory guidance (ref 19). 8.16.7 For the purposes of authorisation this approach can be described as maintaining a condition in which the remaining radiological capacity for a particular nuclide or wastestream, which is proposed for receipt, is greater than zero, taking into account the wastestream received to that point in time. Where: Radiological capacity is the amount of radioactive material that can be consigned to a site without any of the potentially exposed groups considered receiving a dose above a specified criterion, for the specific scenario. For a single radionuclide, the radiological capacity (in Bq) can be easily calculated by dividing the dose criterion (expressed in Sv) by the maximum specific dose for that radionuclide (expressed in Sv/Bq). For mixtures of individual radionuclides, the capacity can be simply apportioned (e.g., half of the overall capacity to each of two radionuclides). In the case of waste streams, however, in which the proportions of different radionuclides are fixed, the calculation of capacity must consider both the specific dose and the activity ratios. The radiological capacity for radionuclide Rni in a waste stream (RCi) is given by: RC i where: DC i SD f Application for disposal of LLW including HV-VLLW under RSA 1993, for the East Northants Resource Management Facility: Supporting Information f i i fi is the fraction of the overall activity arising from Rni (such that fi=1) SDi is the specific dose from Rni DC is the dose constraint Furthermore: Total activity limit for each radionuclide (Bq) = Dose Limit (Sv/y).Waste Activity (Bq) Dose Estimate (Sv/y) July 2009 89 WS010001/ENRMF/CONSAPP<strong>CRF</strong> 408
With the additional constraint that the total dose from all of the radionuclides must not exceed the relevant dose limit: i Qi / Qi,l
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AUGEAN PLC EAST NORTHANTS RESOURCE
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Preface This authorisation applicat
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Wound Exposure 8.5 Pre-Closure - no
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Summary Introduction S1 This docume
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Radioactivity & Risk S12 This summa
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The LLW Disposal Proposal S24 The a
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Key Facts Summary Operational Legal
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S32 The actual capacity of the land
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S40 What are the impacts of transpo
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Annex to the Summary: What is Radio
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How Does Radiation Interact with th
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Supporting Information for the Appl
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2.0 Authorisation 2.1 Background 2.
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management option will allow curren
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Objective/Principle/Requirement fro
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3.1.3 The HPA have recently issued
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Hazardous waste landfills receive w
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easonable attempts have been made t
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3.6.6 This application document doe
Page 39 and 40: 3.10.7 The new regulations to trans
Page 41 and 42: 4.2 Business Plans and Site Develop
Page 43 and 44: upper bound on the region of dose o
Page 45 and 46: proposed that if the waste has an u
Page 47 and 48: y the authorisations for transfer i
Page 49 and 50: 5.4.9 Each package or self-similar
Page 51 and 52: 5.6 Disposal, Waste Emplacement, Co
Page 53 and 54: package and additional shielding (f
Page 55 and 56: 6.0 Waste Disposal History 6.0.1 Th
Page 57 and 58: 8.0 Radioactive Waste Disposal Cons
Page 59 and 60: Scenario Annual Dose Criteria Publi
Page 61 and 62: 8.1.9 Additional ALARA precautions
Page 63 and 64: 8.3 Pre-Closure - not expected to o
Page 65 and 66: Doses from Dropped Load Scenario In
Page 67 and 68: - The crater size can be estimated
Page 69 and 70: 8.5 Pre-Closure - not expected to o
Page 71 and 72: Nuclide Maximum Leachate Authorisat
Page 73 and 74: 8.9 Post-Closure - expected to occu
Page 75 and 76: 8.10 Post-Closure - expected to occ
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Page 81 and 82: Intrusion (Table 5.3, Annex B) "Res
Page 83 and 84: 8.15 Results of the Assessment Scen
Page 85 and 86: 8.16 Landfill Radiological Capacity
Page 87 and 88: Radiological Capacity (MBq) (0.02 m
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Page 93 and 94: Limit values are prescribed for cer
Page 95 and 96: nuclides (including appropriate dau
Page 97 and 98: 10.0 BPEO Assessment for Disposal o
Page 99 and 100: the Environmental Permitting Regula
Page 101 and 102: 12.0 Landfill Engineering and BAT F
Page 103 and 104: 13.0 Waste Hierarchy and Waste Mini
Page 105 and 106: ECOLOGY and NATURE CONSERVATION Woo
Page 107 and 108: 15.2 Augean’s Core Business Value
Page 109 and 110: 15.5 Augean Organisation Group Tech
Page 111 and 112: CPR 04 Off loading of palletised wa
Page 113 and 114: 15.7 Arrangements Specific to LLW D
Page 115 and 116: 17.0 The Application Forms 17.1 Was
Page 117 and 118: References 1 Process and Informatio
Page 119 and 120: Figures Application for disposal of
Page 121 and 122: WS010001/ENRMF/CONSAPPCRF 439
Page 123 and 124: analysis, sensitivity. A quantitati
Page 125 and 126: closure. Administrative and technic
Page 127 and 128: dose. A measure of the energy depos
Page 129 and 130: HPA (NRPB) The Health Protection Ag
Page 131 and 132: model. A representation of a system
Page 133 and 134: adioactive material. Material desig
Page 135 and 136: safety culture. The assembly of cha
Page 137 and 138: uranium, enriched. Uranium containi
Page 139 and 140: Annexes A Radiation, People and the
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WS010001/ENRMF/CONSAPPCRF 459
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the
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Radiological Assessment for Disposa
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Radiological Assessment 0820-2 Vers
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4.3.2 Fire Radiological Assessment
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Annex C ENRMF, IRRs 1999, Radiation
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2 VERSION 3, 14 July 2009 year, and
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2 RADIATION RISKS FROM NORMAL OPERA
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6 VERSION 3, 14 July 2009 Thus, dus
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8 VERSION 3, 14 July 2009 protectio
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10 VERSION 3, 14 July 2009 Access t
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12 VERSION 3, 14 July 2009 clean an
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APPENDIX TO ENRMF RISK ASSESSMENT 1
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Radionuclide Dose coefficient (Sv/B
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Technical Services Group NOT PROTEC
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1 INTRODUCTION NOT PROTECTIVELY MAR
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NOT PROTECTIVELY MARKED Figure 3: D
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4 REFERENCES NOT PROTECTIVELY MARKE
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Annex F Application Form WS010001/E
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Contents A For Office Use B Company
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East Northamptonshire Council Count
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E Type of Application E1 When would
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13.2 Illumination - Use of radiolum
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Please note that Environment Agency
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H6 How do you intend to measure or
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I13 What is the total monthly volum
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J Organic Liquid Waste Accumulation
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Transfer to a contractor Please pro
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Disposal of very low level solid wa
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1 0 Solid waste continued L14 How d
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L29 What is the maximum annual disp
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M2 Do you wish to have the standard
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*Note - These terms are explained i
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Documentary evidence of measures ta
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E-mail S18 What is the address of t
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Please give the county council unle
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Example Capacity Calculation Layout
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Annex H Calculation of dose rate at
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NOT PROTECTIVELY MARKED Table of Co
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NOT PROTECTIVELY MARKED 2.3 MicroSh
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3.3 Covering soil material thicknes
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NOT PROTECTIVELY MARKED APPENDIX A
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Report Determination of 238 U, 235
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Job reference number GAU1278 (Final
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3 H Job reference number GAU1278 (F
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Job reference number GAU1278 (Final
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Annex J Capability Statements WS010
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Peter Shaw Job Title - Group Leader
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Galson Sciences Limited July 2009 D
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1987 - 2005: Director of Environmen
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Appendix CRF - Part 3 - Northamptonshire County Council

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