Appendix CRF - Part 3 - Northamptonshire County Council

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Radiological Capacity (MBq) (0.02 mSv/yr dose criterion) Specific Dose (microSv/yr per MBq) Gas Generation from the Landfill Combined Pre- Closure and Post Closure Public Specific Dose Specific Dose (microSv/yr Specific (microSv/yr per MBq) Specific Dose per MBq) Groundwater Dose (microSv/yr Groundwater Pathway, (microSv/yr per MBq) Pathway, Radiological Site Radiological per MBq) Radiological Intrusion Radiological Borehole, Capacity Boundary Capacity Intrusion Capacity (Table 5.3, Capacity 1500m (MBq) Drinking (MBq) (Table 5.3, (MBq) Annex B) (MBq) Irrigation (0.02 mSv/yr Case, (3 mSv/yr Annex B) (3 mSv/yr "Resident (3 mSv/yr Case (Table dose (Table 5.1 dose "Intruder 60 dose 60 year dose Radionuclide 5.1 Annex B) criterion) Annex B) criterion) year Case" criterion) Case" criterion) Pu-240 1.04E-08 1.92E+09 9.33E-07 3.22E+09 3.82E-05 7.85E+07 1.85E-08 1.62E+11 Pu-241 1.59E-10 1.26E+11 3.62E-08 8.29E+10 1.47E-05 2.04E+08 8.29E-09 3.62E+11 Pu-242 1.69E-08 1.18E+09 1.51E-06 1.99E+09 3.54E-05 8.47E+07 1.76E-08 1.70E+11 6.46E-21 3.10E+21 Am-241 5.37E-11 3.72E+11 1.08E-08 2.78E+11 2.79E-05 1.08E+08 1.57E-08 1.91E+11 Cm-243 1.82E-10 1.10E+11 1.63E-08 1.84E+11 3.03E-06 9.90E+08 4.49E-09 6.68E+11 Cm-244 1.29E-09 1.55E+10 1.15E-07 2.61E+10 1.57E-06 1.91E+09 9.45E-10 3.17E+12 Restrictive Cases for Radiological Capacity on an Individual Nuclide Basis July 2009 87 Application for disposal of LLW including HV-VLLW under RSA 1993, for the East Northants Resource Management Facility: Supporting Information WS010001/ENRMF/CONSAPP<strong>CRF</strong> 406
8.16.5 The likely conclusion is that the landfill can receive unlimited amounts of these nuclides at up to 200 Bq/g without exceeding the radiological capacity before reaching the physical capacity. For those highlighted nuclides their effect in practice will be reduced by being parts of mixtures with other nuclides and at average concentrations less than 200 Bq/g. Several of the most restrictive nuclides are short half-life and will generally not feature in decommissioning wastes in significant concentrations. 8.16.6 Notwithstanding the overall conclusion that capacity is not particularly restricted in this case, the proposal is that the capacity of the landfill is subject to a total capacity limit combined with a series of other conditions. The total capacity limit would apply from the date of issue until closure of the landfill or until the capacity is reached. The landfill would receive no more LLW under the permit once the capacity limit is reached. The capacity limit cannot be expressed as a single number because it depends on the mixture received up to any point in time, so the proposal is for a continuously revised capacity limit based on individual nuclides (including appropriate daughter chains). The total capacity limit would be established using an authorised spreadsheet model agreed with the regulator. The spreadsheet model would represent the most restrictive case from the risk assessment and would produce as an output the remaining capacity of the landfill on an individual nuclide basis given the exact wastes received to that point in time. Prior to accepting any further waste the model would be used by the landfill operator to determine that the consignment would not lead to a breach of the total capacity limit. This approach has a number of features: The approach requires a comprehensive level of waste characterisation by the consignors, but this is considered practicable and is optimal for ensuring public health is not impacted by imprecise waste assay. This is also sustainable because future generations will receive comprehensive information on the disposed nuclides enabling them to make informed decisions. The approach cannot be expressed as a simple number and hence may be less transparent to the public, but the approach is highly transparent and detailed to the regulator. The approach is “modern” in the sense that it aligns the authorisation with the risk assessment. This is in line with proposals to use risk based approaches for RSA exemptions orders, waste definitions, clearance definitions and nuclear site delicensing conditions. Hence the criteria used to produce the waste, to categorise the waste and to dispose of the waste are based on a consistent risk based approach that can be expressed in common terms of risk and dose. The approach is based on the total life cycle of the facility. This addresses a potential public concern that the authorised capacity may “creep” upwards at the point of annual reviews. Authorisation creep of this type was identified as a concern from the pre-application stakeholder workshops. Application for disposal of LLW including HV-VLLW under RSA 1993, for the East Northants Resource Management Facility: Supporting Information July 2009 88 WS010001/ENRMF/CONSAPP<strong>CRF</strong> 407
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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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Page 39 and 40: 3.10.7 The new regulations to trans
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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
Page 77 and 78: Groundwater Pathway, Site Boundary
Page 79 and 80: Intrusion (Table 5.3, Annex B) "Int
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: Radiological Capacity (MBq) (0.02 m
Page 91 and 92: With the additional constraint that
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
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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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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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