Appendix CRF - Part 3 - Northamptonshire County Council

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Radiological Assessment 0820-2 Version 2 groundwater and intrusion. Specific doses through at least one of these routes are higher than the corresponding doses through irradiation, and irradiation will not therefore determine the overall capacity. The aerosol and leachate spillage pathways are all highly uncertain, both in terms of the possibility of occurring and duration. The specific doses presented in Section 5 are illustrative, and might be considered in establishing mitigation measures, but should not be used to determine overall capacities. The specific doses calculated as a result of off-site leachate management are based on a generic model for a sewage treatment plant, with significant uncertainties regarding the extent of dilution by other waste streams and the type and fat of effluents. This model again calculates specific doses based on unit radioactivity inputs. As discussed elsewhere, there are large uncertainties about the rate at which radionuclides would enter the leachate at the ENRMF. Conservative assumptions have been made so that future doses arising from releases to groundwater or accidental spillage of leachate can be calculated. It would, however, be unreasonable to apply these same assumptions to the routine management of leachate during the operational period. Even if the same generic model for the sewage treatment plant is used to estimate specific doses, it would be more appropriate to determine a permissible level of radioactivity in leachate and then to develop authorisation conditions from these. Monitoring of leachate would ensure compliance with these conditions and give more control than applying conservative assumptions. As discussed in Section 3.2.1, two dose criteria have been used to determine radiological capacity. For exposures arising from releases to groundwater and subsequent use of an existing borehole for irrigation purposes, a dose criterion of 20 Sv / year has been used. For exposures resulting from intrusion into the waste, from excavation and subsequent use of waste as soil, and from consumption of groundwater extracted from close to the site boundary, a dose criterion of 3 mSv / year has been used. 6.2 Radionuclide-specific radiological capacities Tables 6.1 to 6.3 present specific doses and the corresponding radionuclide-specific capacities for the two groundwater pathways and the principal intrusion pathway described in Sections 4 and 5. Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) H-3 3.66E-30 5.47E+30 Ra-226 1.56E-08 1.28E+09 C-14 2.06E-09 9.69E+09 Ac-227 5.66E-26 3.53E+26 Cl-36 6.52E-08 3.07E+08 Th-229 1.44E-08 1.39E+09 Fe-55 1.04E-43 1.92E+44 Th-230 8.24E-09 2.43E+09 Co-60 1.21E-39 1.65E+40 Th-232 4.04E-08 4.95E+08 Galson Sciences Limited 60 14 July 2009 WS010001/ENRMF/CONSAPP<strong>CRF</strong> 610
Radiological Assessment 0820-2 Version 2 Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) Ni-63 7.94E-21 2.52E+21 Pa-231 3.60E-08 5.56E+08 Sr-90 3.04E-24 6.59E+24 U-232 5.07E-20 3.94E+20 Nb-94 3.76E-10 5.33E+10 U-233 4.62E-09 4.33E+09 Tc-99 2.12E-09 9.45E+09 U-234 4.35E-09 4.60E+09 Ru-106 3.44E-46 5.81E+46 U-235 4.35E-09 4.60E+09 Ag-108m 1.68E-17 1.19E+18 U-236 4.22E-09 4.74E+09 Sb-125 4.81E-42 4.16E+42 U-238 4.35E-09 4.59E+09 Sn-126 1.20E-08 1.67E+09 Np-237 1.22E-06 1.64E+07 I-129 1.38E-05 1.45E+06 Pu-238 1.86E-12 1.07E+13 Ba-133 1.44E-31 1.39E+32 Pu-239 1.54E-08 1.30E+09 Cs-134 1.82E-43 1.10E+44 Pu-240 1.04E-08 1.92E+09 Cs-137 1.28E-25 1.57E+26 Pu-241 1.59E-10 1.26E+11 Pm-147 3.41E-44 5.87E+44 Pu-242 1.69E-08 1.19E+09 Eu-152 2.77E-32 7.21E+32 Am-241 5.37E-11 3.73E+11 Eu-154 3.28E-35 6.09E+35 Cm-243 1.82E-10 1.10E+11 Eu-155 3.63E-41 5.50E+41 Cm-244 1.29E-09 1.55E+10 Pb-210 1.25E-25 1.60E+26 Table 6.1 Specific doses to members of the public via use of water from a borehole 1500 m from the site boundary for irrigation, and corresponding radiological capacities. Radiological capacities are based on a 20 Sv / year dose criterion. Results include doses arising from ingrowth of daughter radionuclides for 100 years. Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) Radionuclide Specific dose (μSv y -1 per MBq) Radiological capacity (MBq) H-3 6.89E-23 4.36E+25 Ra-226 1.36E-06 2.20E+09 C-14 1.39E-07 2.16E+10 Ac-227 6.70E-19 4.48E+21 Cl-36 1.69E-06 1.78E+09 Th-229 1.29E-06 2.33E+09 Fe-55 4.45E-36 6.74E+38 Th-230 7.35E-07 4.08E+09 Co-60 3.79E-32 7.91E+34 Th-232 3.59E-06 8.36E+08 Ni-63 3.47E-15 8.65E+17 Pa-231 3.08E-06 9.74E+08 Sr-90 2.19E-17 1.37E+20 U-232 6.19E-14 4.85E+16 Galson Sciences Limited 61 14 July 2009 WS010001/ENRMF/CONSAPP<strong>CRF</strong> 611
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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
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3.10.7 The new regulations to trans
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4.2 Business Plans and Site Develop
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upper bound on the region of dose o
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proposed that if the waste has an u
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y the authorisations for transfer i
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5.4.9 Each package or self-similar
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5.6 Disposal, Waste Emplacement, Co
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package and additional shielding (f
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6.0 Waste Disposal History 6.0.1 Th
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8.0 Radioactive Waste Disposal Cons
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Scenario Annual Dose Criteria Publi
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8.1.9 Additional ALARA precautions
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8.3 Pre-Closure - not expected to o
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Doses from Dropped Load Scenario In
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- The crater size can be estimated
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8.5 Pre-Closure - not expected to o
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Nuclide Maximum Leachate Authorisat
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8.9 Post-Closure - expected to occu
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8.10 Post-Closure - expected to occ
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Groundwater Pathway, Site Boundary
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Intrusion (Table 5.3, Annex B) "Int
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Intrusion (Table 5.3, Annex B) "Res
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8.15 Results of the Assessment Scen
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8.16 Landfill Radiological Capacity
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Radiological Capacity (MBq) (0.02 m
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8.16.5 The likely conclusion is tha
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With the additional constraint that
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Limit values are prescribed for cer
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nuclides (including appropriate dau
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10.0 BPEO Assessment for Disposal o
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the Environmental Permitting Regula
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12.0 Landfill Engineering and BAT F
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13.0 Waste Hierarchy and Waste Mini
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ECOLOGY and NATURE CONSERVATION Woo
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15.2 Augean’s Core Business Value
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15.5 Augean Organisation Group Tech
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CPR 04 Off loading of palletised wa
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15.7 Arrangements Specific to LLW D
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17.0 The Application Forms 17.1 Was
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References 1 Process and Informatio
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Figures Application for disposal of
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WS010001/ENRMF/CONSAPPCRF 439
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analysis, sensitivity. A quantitati
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closure. Administrative and technic
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dose. A measure of the energy depos
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HPA (NRPB) The Health Protection Ag
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model. A representation of a system
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adioactive material. Material desig
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safety culture. The assembly of cha
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uranium, enriched. Uranium containi
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Annexes A Radiation, People and the
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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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Page 241 and 242: Radiological Assessment 0820-2 Vers
Page 273 and 274: 4.3.2 Fire Radiological Assessment
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Page 323 and 324: Annex C ENRMF, IRRs 1999, Radiation
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Page 335 and 336: 12 VERSION 3, 14 July 2009 clean an
Page 337 and 338: APPENDIX TO ENRMF RISK ASSESSMENT 1
Page 339 and 340: Radionuclide Dose coefficient (Sv/B
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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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