1. In this Part—
“Ba-137m eluting source” means a source which consists of Cs-137 in a sealed container which is designed and constructed to allow the elution of Ba-137m, and which is radioactive material or radioactive waste solely because of that Cs-137;
“Class A gaseous tritium light device” means a gaseous tritium light device where the activity of the device does not exceed 2 x 1010 Bq of tritium;
“Class B gaseous tritium light device” means a gaseous tritium light device which is installed or intended to be installed on premises and where the activity—
in each sealed container in the device does not exceed 8 x 1010 Bq of tritium, and
of the device does not exceed 1 x 1012 Bq of tritium;
“Class C gaseous tritium light device” means a gaseous tritium light device installed or intended to be installed—
in a vessel or aircraft, or
in a vehicle or other equipment used or intended to be used by the armed forces of the Crown;
“disposal permit” means—
an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule, or
an authorisation under the 1993 Act to dispose of radioactive waste held in respect of premises situated in Northern Ireland or Scotland;
“electrodeposited source” means an article where radionuclides are electrodeposited onto a metal substrate and which is radioactive material or radioactive waste solely because it contains Ni-63 or Fe-55;
“gaseous tritium light device” means a sealed source in a device which is an illuminant, instrument, sign or indicator which—
incorporates tritium in one or more sealed containers constructed to prevent dispersion of that tritium in normal use, and
is radioactive material solely because it contains that tritium;
“luminised article” means an article which is made wholly or partly from a luminescent substance in the form of a film or a paint and which—
is radioactive material or radioactive waste solely because it contains Pm-147 or H-3, and
is not a sealed source;
“management”, in respect of waste, means—
the preparation by checking, cleaning or repairing that waste for its re-use without further processing,
the recovery of that waste,
the disposal of that waste, or
the application of any treatment process to that waste which is preparatory to the recovery or disposal of it,
and cognate expressions shall be construed accordingly;
“relevant river” means a river or a part of a river which—
is not a part of the sea, and
at the place and time of any disposal into it of aqueous radioactive waste from a sewage disposal works or directly from premises, has a flow-rate which is not less than 1m3s-1;
“relevant sewer” means—
a public sewer, or
a disposal main which leads to a sewage disposal works that—
has the capacity to handle a minimum of 100m3 of effluent per day, and
discharges treated effluent only to the sea or to a relevant river,
and “public sewer”, “disposal main”, “sewage disposal works” and “effluent” have the same meaning as in the Water Industry Act 1991 M1;
“relevant standard conditions” has the meaning given in paragraph 10;
“sea” includes any area submerged at mean high water springs and also includes, so far as the tide flows at mean high water springs, an estuary or arm of the sea and the waters of any channel, creek, bay or river;
“sealed source” means a radioactive source containing radioactive material where the structure is designed to prevent, under normal use, any dispersion of radioactive substances, excluding such a source where it is an electrodeposited source or a tritium foil source;
“stored in transit” means the storage in the course of transit of radioactive material or radioactive waste but does not include any storage of such material or waste where it is removed from its container;
“Table 4”, “Table 5”, “Table 6”, “Table 7” or “Table 8” means the table with that number in this Part;
“a tritium foil source” means an article which—
has a mechanically tough surface into which tritium is incorporated, and
is radioactive material or radioactive waste solely because of that tritium;
“uranium or thorium compound” means a substance or article which is radioactive material or radioactive waste solely because it is or contains metallic uranium or thorium or prepared compounds of uranium or thorium, and in respect of which metal or compound the proportion of—
U-235 in the uranium it contains is no more than 0.72% by mass, and
any isotope of thorium it contains is present in the isotopic proportions found in nature;
“waste permitted person” means, in relation to the radioactive waste where the term appears, a person who holds—
an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) or (c) of Part 2 of this Schedule, or
in respect of premises in Scotland or Northern Ireland, an authorisation under section 13 or 14 of the 1993 Act;
“week” means any period of 7 consecutive days;
“year” means a calendar year.
Marginal Citations
M11991 c. 56; the definition of “public sewer” was amended by section 99(6) of the Water Act 2003 (c. 37).
2.—(1) In this Part, “NORM waste” means a substance or article which is solid radioactive waste under—
(a)paragraph 4 of Part 2 of this Schedule, or
(b)except where sub-paragraph (2) applies, paragraph 5 of that Part where the waste arises from the remediation of land.
(2) Land is not contaminated under sub-paragraph (1)(b) where the land is on a site in respect of which a nuclear site licence is or has been in force and the contamination occurred—
(a)when that licence was in force, or
(b)before that licence was granted, when the site was used for the purpose of installing or operating an installation described in subsection (1) of section 1 of the Nuclear Installations Act 1965 M2 or in regulations made under that subsection.
(3) In these Regulations, “NORM waste concentration” means, in respect of radionuclides contained in NORM waste, the sum of the concentrations of the single radionuclide with the highest concentration in each of the natural decay chains beginning with—
(a)U-238,
(b)U-235, and
(c)Th-232.
Marginal Citations
M21965 c. 57; section 1 was substituted by paragraph 17 of Part 2 of Schedule 12 to the Energy Act 2013 (c. 32).
3.—(1) A person (“A”) is exempt from the requirement for an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(a) of Part 2 of this Schedule in respect of—
(a)subject to sub-paragraph (2), the radioactive material described in paragraph 5, where A complies with the relevant standard conditions and—
(i)in respect of radioactive material described in paragraph 5(1)(a), the condition in paragraph 6(1), and
(ii)in respect of radioactive material described in paragraph 5(1)(b), the condition in paragraph 6(2), or
(b)radioactive material stored in transit.
(2) A is not exempt from the requirement for an environmental permit under sub-paragraph (1)(a) in respect of a high activity source where A takes possession of it.
4.—(1) This paragraph applies to the following radioactive substances activities—
(a)the activity described in paragraph 11(2)(c) of Part 2 of this Schedule (“Activity A”), and
(b)the activity described in paragraph 11(4) of Part 2 of this Schedule (“Activity B”).
(2) In this paragraph, “paragraph 5 waste” means radioactive waste described in paragraph 5.
(3) A person (“A”) is exempt from the requirement for an environmental permit to carry on Activity A or B, in respect of radioactive waste which is stored in transit.
(4) Subject to sub-paragraph (5), a person (“B”) is exempt from the requirement for an environmental permit to carry on Activity A or B in respect of paragraph 5 waste where—
(a)B receives that waste for accumulation on premises (with a view to its subsequent management by B on those premises),
(b)in respect of those premises B manages substantial quantities of waste which is not radioactive waste, and
(c)the management of the radioactive waste will be completed by B as soon as is reasonably practicable, with the radioactive waste dispersed in non-radioactive waste.
(5) B is not exempt under sub-paragraph (4) from the requirement for an environmental permit to carry on Activity B where the waste received by B is or contains a high-activity source.
(6) A person (“C”) is exempt from the requirement for an environmental permit to carry on Activity A in respect of paragraph 5 waste, where C complies with the relevant standard conditions and—
(a)in respect of radioactive waste described in paragraph 5(1)(a), the condition in paragraph 6(1), and
(b)in respect of radioactive waste described in paragraph 5(1)(b), the condition in paragraph 6(2).
(7) A person (“D”) is exempt from the requirement for an environmental permit to carry on Activity A in respect of radioactive waste which is a sealed source, an electrodeposited source or a tritium foil source which—
(a)contains a quantity of radionuclides which exceeds the value specified in column 2 of Table 4 in respect of the relevant type of source,
(b)immediately before it became radioactive waste, was radioactive material in the form of a sealed source, an electrodeposited source or a tritium foil source (as appropriate), and
(c)has not been received by D for the purpose of D disposing of it,
where D complies with the relevant standard conditions.
5.—(1) Subject to sub-paragraph (2), paragraphs 3(1)(a) and 4(4) and (6) apply to—
(a)a substance or article described in an entry in column 1 of Table 4 which contains a quantity of radionuclides that does not exceed the value specified in column 2 of Table 4 in respect of that substance or article, or
(b)any substance or article which is not described in an entry in column 1 of Table 4.
(2) Sub-paragraph (1) does not apply to NORM waste with a NORM waste concentration which is less than or equal to 10 Bq/g.
6.—(1) The condition referred to in paragraphs 3(1)(a)(i) and 4(6)(a) is that, in respect of the total amount of a substance or article described in paragraph 5(1)(a) (including any mobile radioactive apparatus) on the premises, the quantity of radionuclides must not exceed the value specified for that substance or article in column 3 of Table 4.
(2) The condition referred to in paragraphs 3(1)(a)(ii) and 4(6)(b) in respect of a substance or article described in paragraph 5(1)(b) is that—
(a)in respect of the total amount of such substances and articles on the premises, the quantity of radioactivity does not exceed the value specified in column 2 of Table 5, or
(b)no such substance or article on the premises contains a concentration of radioactivity that exceeds the value specified in column 3 of Table 5.
7.—(1) This paragraph applies—
(a)to the following radioactive substances activities—
(i)the activity described in paragraph 11(2)(c) of Part 2 of this Schedule (“Activity A”);
(ii)the activity described in paragraph 11(4) of Part 2 of this Schedule (“Activity B”), and
(b)where Activity A or B is carried on in respect of NORM waste with a NORM waste concentration that does not exceed 10 Bq/g (“Qualifying NORM Waste”).
(2) Subject to sub-paragraph (5) where it applies, a person (“A”) is exempt from the requirement for an environmental permit to carry on Activity A or Activity B in respect of Qualifying NORM Waste, where another person (“B”) transfers that waste to A—
(a)in accordance with—
(i)a disposal permit held by B, or
(ii)an exemption from holding such a permit that applied to B in respect of the transfer to A, and
(b)for the purpose of its accumulation by A with a view to its subsequent management by A on the premises on which it is received by A.
(3) Subject to sub-paragraph (5) where it applies, a person (“C”) is exempt from the requirement for an environmental permit to carry on Activity A in respect of Qualifying NORM Waste where C complies with the relevant standard conditions.
(4) Sub-paragraph (5) applies to a person (“D”) who holds an environmental permit to carry on Activity A on premises (“the relevant premises”) in respect of NORM waste with a NORM waste concentration which is more than 10 Bq/g.
(5) The exemptions in sub-paragraphs (2) and (3) do not apply to D in respect of Qualifying NORM waste—
(a)with a NORM waste concentration which exceeds 5 Bq/g, and
(b)which is accumulated on the relevant premises.
8.—(1) A person (“A”) is exempt from the requirement for an environmental permit to carry on the radioactive substances activity described in paragraph 11(5) of Part 2 of this Schedule in respect of—
(a)a mobile radioactive apparatus described in an entry in column 1 of Table 4 where—
(i)that apparatus contains a quantity of radionuclides that does not exceed the value specified in column 2 of Table 4 in respect of an apparatus of that description, and
(ii)A complies with the conditions in sub-paragraph (2), or
(b)mobile radioactive apparatus stored in transit.
(2) The conditions in this sub-paragraph are that A must—
(a)ensure that in relation to the total amount of all such mobile radioactive apparatus that A holds, the quantity of radionuclides does not exceed the value specified, in respect of an apparatus of that description, in column 3 of Table 4, and
(b)comply with the relevant standard conditions.
9. In this Section, “radioactive substances” means radioactive material, mobile radioactive apparatus and radioactive waste, and “exempt radioactive substances” means radioactive substances in respect of which an exemption in Section 2 or 3 of this Part applies.
10.—(1) Reference to the relevant standard conditions in Sections 1 to 3 of this Part, means in respect of the exemption provided for in—
(a)paragraph 3(1)(a), the conditions in paragraphs 11 and 12;
(b)paragraph 4(6), 4(7) or 7(3), the conditions in paragraphs 11, 12 and 14;
(c)paragraph 8(1)(a), the conditions in paragraphs 11 and 13.
(2) A condition in paragraph 11, 12 or 13 does not apply in respect of an exemption in Section 2 or 3 of this Part unless that condition is a relevant condition in respect of that exemption.
11. A person (“A”) to whom the conditions in this paragraph apply must—
(a)keep an adequate record of any exempt radioactive substances which A holds, and—
(i)in respect of exempt radioactive substances which are mobile radioactive apparatus, the locations at which they are kept or used;
(ii)in respect of other exempt radioactive substances, the location within the premises where A holds them,
(b)ensure that where reasonably practicable exempt radioactive substances or the containers of such radioactive substances, are marked or labelled as radioactive,
(c)in respect of exempt radioactive substances which are sealed sources, electrodeposited sources or tritium foil sources, not modify or mutilate those sources or cause a loss of containment such that radioactive material or radioactive waste may be released outside the source,
(d)allow the regulator access to such records or such premises as the regulator may request in order to determine that all of the conditions in respect of the relevant exemption are complied with,
(e)hold the exempt radioactive substances safely and securely to prevent, so far as reasonably practicable—
(i)accidental removal, loss or theft from the premises where they are held, or
(ii)loss of containment, and
(f)in respect of exempt radioactive substances in a container—
(i)not modify or mutilate that container, and
(ii)prevent any uncontrolled or unintended release of radioactive material or radioactive waste from the container.
12.—(1) Subject to sub-paragraph (2), in the event of an incident of loss or theft (or suspected loss or theft) of exempt radioactive substances (except mobile radioactive apparatus) from the premises where they are held, a person to whom the condition in this paragraph applies must—
(a)notify the incident to the regulator as soon as reasonably practicable, and
(b)include in that notification the details of any other incidents of loss or theft (or suspected loss or theft) of any radioactive substances from those premises over the 12 months preceding the incident being notified.
(2) In respect of an incident described in sub-paragraph (1), a notification to the regulator is not required where in respect of the aggregated total amount of exempt radioactive substances (excluding mobile radioactive apparatus) lost or stolen (or suspected to have been lost or stolen) from the premises in the incident and in all other such incidents in the 12 months preceding it, the total quantity of radioactivity does not exceed the value that is ten times the value in column 2 of Table 5.
13.—(1) Subject to sub-paragraph (2), in the event of an incident of loss or theft (or suspected loss or theft) of mobile radioactive apparatus from a person (“A”) to whom the condition in this paragraph applies, A must—
(a)notify the incident to the regulator as soon as reasonably practicable, and
(b)include in that notification the details of any other incidents of loss or theft (or suspected loss or theft) of any mobile radioactive apparatus from A over the 12 months preceding the incident being notified.
(2) In respect of an incident described in sub-paragraph (1), a notification to the regulator is not required where in respect of the aggregated total amount of mobile radioactive apparatus lost or stolen (or suspected to have been lost or stolen) from A in the incident and in all other such incidents in the 12 months preceding it, the total quantity of radioactivity does not exceed the value that is ten times the value in column 2 of Table 5.
14. A person to whom the condition in this paragraph applies must dispose of the radioactive waste which is the subject of the exemption to which this condition applies—
(a)as soon as reasonably practicable after it has become waste, and
(b)in the case of such waste where it is a sealed source, a tritium foil source or an electrodeposited source, in any event within 26 weeks after it has become waste unless the regulator advises in writing that a longer period of accumulation is allowed.
15.—(1) This paragraph applies to the following radioactive substances activities—
(a)the activity described in paragraph 11(2)(b) of Part 2 of this Schedule (“Activity A”);
(b)the activity described in paragraph 11(4) of Part 2 of this Schedule (“Activity B”).
(2) A person (“A”) is exempt from the requirement for an environmental permit to carry on Activity A or Activity B in respect of solid radioactive waste described in paragraph 16(1)(a) where—
(a)A receives the waste on premises for the purpose of it being managed by A on those premises,
(b)in respect of those premises A manages substantial quantities of waste which is not radioactive waste, and
(c)the radioactive waste will be disposed of by A as soon as is reasonably practicable with the radioactive waste dispersed in non-radioactive waste.
(3) A person (“B”) is exempt from the requirement for an environmental permit to carry on Activity A in respect of solid radioactive waste described in paragraph 16(1) where—
(a)in respect of a sealed source, an electrodeposited source or a tritium foil source, B complies with the conditions in paragraph 17(2), and
(b)in respect of any other waste described in paragraph 16(1)(a), B complies with the conditions in paragraph 17(1) and (2).
16.—(1) Solid radioactive waste referred to in paragraph 15 means—
(a)subject to sub-paragraph (2), solid radioactive waste described in an entry in column 1 of Table 6 which does not contain a concentration of radionuclides that exceeds the value specified in column 2 of that table in respect of that kind of waste, or
(b)a sealed source, an electrodeposited source or a tritium foil source which is not described in paragraph (a).
(2) Sub-paragraph (1)(a) does not apply to waste—
(a)where, prior to the disposal of that waste, a person has diluted it with the intention of ensuring that sub-paragraph (1)(a) is met, or
(b)which is NORM waste with a NORM waste concentration which is less than or equal to 10 Bq/g.
17.—(1) The condition referred to in paragraph 15(3)(b) is that B must ensure that, in respect of the total amount of a waste to which this condition applies that is disposed of on or from the premises, the quantity of radioactivity which that waste contains must not exceed the value specified in column 3 of Table 6 in respect of that waste during the period stated in that column.
(2) The conditions referred to in paragraph 15(3)(a) and (b) are that B must—
(a)keep an adequate record of the solid radioactive waste which B disposes of on or from any premises under that paragraph,
(b)dispose of the waste by any of the routes described in sub-paragraph (3),
(c)where the disposal route in sub-paragraph (3)(a) is used, ensure that where reasonably practicable any marking or labelling of the waste or its container is removed before the person disposes of that waste,
(d)where the waste is or was a high-activity source, notify the details of the disposal to the regulator within 14 days of the disposal (including the information required by Annex II to the HASS Directive), in such form as may be required by the regulator, and
(e)allow the regulator access to such records or such premises as the regulator may request in order to determine that all of the conditions that apply in respect of the relevant exemption in paragraph 15(3) are complied with.
(3) The routes referred to in sub-paragraph (2)(b) are that the waste is transferred to—
(a)subject to sub-paragraph (4), a person who manages substantial quantities of non-radioactive waste and where the radioactive waste will be so managed with the radioactive waste dispersed in non-radioactive waste,
(b)a waste permitted person, or
(c)where the waste is a sealed source, an electrodeposited source or a tritium foil source, to a licensee of a nuclear site or to a person who is situated in another country and who is lawfully entitled to receive such waste.
(4) The route in sub-paragraph (3)(a) does not apply in respect of waste—
(a)described in paragraph 16(1)(b), or
(b)which is described in paragraph 16(1)(a) and which is a sealed source, an electrodeposited source or a tritium foil source, where in respect of the total amount of such a source which is disposed of on or from the premises under paragraph 15(3), the quantity of radioactivity which that waste contains exceeds the value specified in column 3 of Table 6 in respect of that source during the period stated in that column.
18.—(1) This paragraph applies—
(a)to the following radioactive substances activities—
(i)the activity described in paragraph 11(2)(b) of Part 2 of this Schedule (“Activity A”);
(ii)the activity described in paragraph 11(4) of Part 2 of this Schedule (“Activity B”), and
(b)where Activity A or B is carried on in respect of NORM waste—
(i)with a NORM waste concentration that does not exceed 5 Bq/g (“type 1 NORM Waste”), or
(ii)with a NORM waste concentration that exceeds 5 Bq/g but does not exceed 10 Bq/g (“type 2 NORM waste”).
(2) Subject to sub-paragraph (6), a person (“A”) is exempt from the requirement for an environmental permit to carry on Activity A or Activity B in respect of type 1 NORM waste or type 2 NORM waste where another person (“B”) transfers that waste to A—
(a)in accordance with—
(i)a disposal permit held by B, or
(ii)an exemption from holding such a permit that applied to B in respect of the transfer to A, and
(b)for the purpose of its disposal by A on the premises on which A receives it.
(3) Where a person (“C”) disposes of—
(a)type 1 NORM waste on or from premises, sub-paragraph (4) applies to C, or
(b)type 2 NORM waste on or from premises, sub-paragraph (5) applies to C.
(4) C is exempt from the requirement for an environmental permit to carry on Activity A in respect of type 1 NORM waste where in relation to the total amount of such waste disposed of on or from the premises by C per year—
(a)the quantity of radionuclides does not exceed 5 x 1010 Bq, and C complies with the conditions in paragraph 19(1), or
(b)subject to sub-paragraph (6), the quantity of radionuclides exceeds 5 x 1010 Bq, and C complies with—
(i)the conditions in paragraph 19(1), and
(ii)where C intends to dispose of the waste by one of the methods in paragraph 19(2)(a), the conditions in paragraph 19(3).
(5) Subject to sub-paragraph (6), C is exempt from the requirement for an environmental permit to carry on Activity A in respect of type 2 NORM waste where C complies with the conditions in paragraph 19(1) and (3).
(6) Sub-paragraph (7) applies to a person (“E”) where E holds an environmental permit to carry on Activity A for the disposal on or from premises (“the relevant premises”) of NORM waste with a NORM waste concentration which exceeds 10 Bq/g.
(7) The following exemptions do not apply to E—
(a)the exemptions in sub-paragraph (2) in respect of type 2 NORM waste,
(b)the exemption in sub-paragraph (4)(b), and
(c)the exemption in sub-paragraph (5).
19.—(1) The conditions referred to in the exemptions in paragraph 18(4)(a) and (b)(i) and (5) are that C must—
(a)keep an adequate record of the NORM waste which C disposes of under those exemptions,
(b)dispose of the waste by any of the methods described in sub-paragraph (2),
(c)where the disposal method in sub-paragraph (2)(a) or (b) is used, ensure that where reasonably practicable any marking or labelling of the waste or its container is removed before C disposes of that waste, and
(d)allow the regulator access to such records or such premises as the regulator may request in order to determine that all of the conditions that apply to C in respect of the relevant exemption in that paragraph are complied with.
(2) The methods referred to in sub-paragraph (1)(b) are that the waste is disposed of—
(a)subject to sub-paragraph (3) where it applies, by burial in landfill or by the transfer of the waste to a person for the purpose of—
(i)the burial in landfill of the waste, or
(ii)the application of a treatment process to the waste which is preparatory to the burial in landfill of that waste,
(b)by incineration (or transfer to a person for such incineration or treatment which is preparatory to the incineration of the waste), but not in respect of—
(i)type 1 NORM waste, where in respect of the total amount of that waste that is incinerated (or transferred to a person for preparation or incineration) per year the quantity of radionuclides in the total amount of that waste exceeds 1 x 108 Bq, or
(ii)type 2 NORM waste, or
(c)by transfer to a waste permitted person.
(3) The conditions referred to in paragraph 18(4)(b)(ii) and (5) are that C must—
(a)make a written radiological assessment of the reasonably foreseeable pathways for the exposure of the public and workers to radiation in respect of—
(i)the application of any treatment process to the waste which is preparatory to its burial in landfill, at the place of that treatment, and
(ii)the burial in landfill of that waste, at the place of disposal,
(b)be satisfied that the assessment demonstrates that radiation doses are not expected to exceed—
(i)1 millisievert per year to any worker at the place of treatment or disposal, and
(ii)300 microsievert per year to any member of the public,
(c)provide that assessment to the regulator at least 28 days before the first disposal is made, and
(d)not dispose of that waste (or continue to do so) if the regulator objects in writing to that assessment.
20.—(1) Subject to sub-paragraph (2), a person (“A”) is exempt from the requirement for an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule in respect of aqueous radioactive waste described in an entry in column 1 of Table 6, where A complies with the conditions in sub-paragraph (3).
(2) A is not exempt under sub-paragraph (1) where the person who generated that waste did not minimise the quantity of radionuclides generated as waste to the extent reasonably practicable.
(3) The conditions referred to in sub-paragraph (1) are that, in respect of the waste described in that sub-paragraph, A must—
(a)ensure that in respect of the total amount of that waste that is disposed of on or from the premises in a year, the quantity of radioactivity which that waste contains does not exceed the value specified in column 3 of Table 6 in respect of that waste,
(b)dispose of that waste to a relevant sewer or to a waste permitted person,
(c)keep an adequate record of that waste which A disposes of on or from the premises, and
(d)allow the regulator access to such records or such premises as the regulator may request in order to determine that the preceding conditions in this sub-paragraph are complied with.
21.—(1) Subject to sub-paragraph (2), a person (“A”) is exempt from the requirement for an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule in respect of aqueous radioactive waste described in sub-paragraph (3) where A disposes of that waste in accordance with the conditions in paragraph 22(1).
(2) A is not exempt under sub-paragraph (1) in respect of premises, where A holds an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule for the disposal of aqueous radioactive waste on or from those premises.
(3) Subject to sub-paragraph (4), the waste referred to in sub-paragraph (1) is aqueous radioactive waste—
(a)which is not described in an entry in column 1 of Table 6, and
(b)with a total concentration of radioactivity which does not exceed 100 Bq/ml.
(4) Sub-paragraph (3) does not apply to aqueous radioactive waste—
(a)which a person has diluted with the intention that—
(i)the waste has a concentration of radioactivity which is below the value in sub-paragraph (3)(b), or
(ii)the condition in paragraph 22(3)(a) or (4)(b) is complied with in respect of that waste, or
(b)where the person who generated that waste did not minimise the quantity of radionuclides generated as waste to the extent reasonably practicable.
22.—(1) The conditions referred to in paragraph 21(1) are that A must—
(a)subject to sub-paragraph (2), dispose of the waste to which that paragraph applies—
(i)directly into a relevant river or the sea,
(ii)to a relevant sewer, or
(iii)to a waste permitted person,
(b)keep an adequate record of the waste which A disposes of from the premises under that paragraph,
(c)in respect of the disposal of aqueous non-Table 6 waste, comply with sub-paragraph (3) or (4) as appropriate, and
(d)allow the regulator access to such records or such premises as the regulator may request in order to determine that all of the preceding conditions are complied with.
(2) In respect of aqueous non-Table 6 waste disposed of from the premises, A must not use both of the disposal routes described in sub-paragraph (1)(a)(i) and (ii) in a year and where—
(a)A uses the route in sub-paragraph (1)(a)(i), the conditions in sub-paragraph (3) apply to A, or
(b)A uses the route in sub-paragraph (1)(a)(ii), or A does not use the route in either sub-paragraph (1)(a)(i) or (ii), the conditions in sub-paragraph (4) apply to A.
(3) Where this sub-paragraph applies and A disposes of the aqueous non-Table 6 waste directly into a relevant river or the sea, A must—
(a)in respect of any aqueous non-Table 6 waste which A disposes of, ensure that the concentration of radioactivity does not exceed the value specified in column 2 of Table 7, and
(b)in respect of the total amount of aqueous non-Table 6 waste which A disposes of from the premises in a year, ensure that the quantity of radioactivity does not exceed the value specified in column 4 of Table 7.
(4) Where this sub-paragraph applies and A disposes of the aqueous non-Table 6 waste to a relevant sewer (or only to a waste permitted person), A must ensure that, in respect of the total amount of aqueous non-Table 6 waste which is disposed of from those premises in a year, the total quantity of radioactivity does not exceed—
(a)where any of that waste has a concentration of radioactivity which exceeds the value specified in column 2 of Table 7, the value in sub-paragraph (5), or
(b)where none of that waste has a concentration of radioactivity which exceeds the value specified in column 2 of Table 7, the value in sub-paragraph (5) or (6).
(5) The value referred to in sub-paragraph (4)(a) and (b) is—
(a)1 x 108 Bq for the sum of the following radionuclides: H-3, C-11, C-14, F-18, P-32, P-33, S-35, Ca-45, Cr-51, Fe-55, Ga-67, Sr-89, Y-90, Tc-99m, In-111, I-123, I-125, I-131, Sm-153, Tl-201, and
(b)1 x 106 Bq for the sum of all other radionuclides.
(6) The value referred to in sub-paragraph (4)(b) is the value specified in column 3 of Table 7.
(7) In this paragraph, “aqueous non-Table 6 waste” means aqueous radioactive waste which is not described in an entry in column 1 of Table 6.
23.—(1) Subject to sub-paragraph (2), a person (“A”) is exempt from the requirement for an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule in respect of gaseous radioactive waste where—
(a)the only radionuclide contained in that waste is Kr-85 and A—
(i)ensures that in respect of the total amount of such waste which is disposed of from the premises in a year, the total quantity of radioactivity does not exceed 1011 Bq, and
(ii)complies with the conditions in paragraph 24(1), or
(b)subject to sub-paragraph (3), that waste—
(i)is released from within a container at the time that the container is opened, and
(ii)is emitted by solid or liquid radioactive material within the container,
and A complies with the conditions in paragraph 24(1).
(2) Sub-paragraph (1) does not apply to waste where the person who generated that waste did not minimise the quantity of radionuclides generated as waste to the extent reasonably practicable.
(3) Sub-paragraph (1)(b) does not apply in respect of any gas which arises as a result of a process applied by a person to the contained radioactive material.
24.—(1) The conditions referred to in paragraph 23(1) are that A must—
(a)to the extent that is reasonably practicable—
(i)in respect of relevant gaseous waste which arises in a building, cause the waste to be disposed of by an extraction system which removes the waste from the area where it arose and which vents the waste into the atmosphere, and
(ii)prevent the entry or, where sub-paragraph (i) applies, the re-entry, of relevant gaseous waste into a building, and
(b)allow the regulator access to such records or such premises as the regulator may request in order to determine that all of the conditions that apply to A in respect of the relevant exemption in that paragraph are complied with.
(2) In this paragraph “relevant gaseous waste” means waste which is described in paragraph 23(1) and disposed of under the exemption in that paragraph.
25. The Table 4 referred to in Sections 2 and 3 of this Part—
| Substance or article | Maximum quantity of radionuclides for each substance or article | Maximum quantity of radionuclides: |
|---|---|---|
| (a) on any premises in items which satisfy the limit in column 2, or | ||
| (b) in mobile radioactive apparatus held by a person | ||
| A sealed source of a type not described in any other row of this Table | 4 x 106 Bq | 2 x 108 Bq |
| A Class A gaseous tritium light device | 2 x 1010 Bq | 5 x 1012 Bq |
| A Class B gaseous tritium light device | 1 x 1012 Bq | 3 x 1013 Bq |
| A Class C gaseous tritium light device | 1 x 1012 Bq | No limit |
| Any sealed source which is solely radioactive material or radioactive waste because it contains tritium | 2 x 1010 Bq | 5 x 1012 Bq |
| A tritium foil source | 2 x 1010 Bq | 5 x 1012 Bq |
| A smoke detector affixed to premises | 4 x 106 Bq | No limit |
| An electrodeposited source | 6 x 108 Bq Ni-63 or 2 x 108 Bq Fe-55 | 6 x 1011 Bq |
| A luminised article | 8 x 107 Bq Pm-147 or 4 x 109 Bq H-3 | 4 x 1010 Bq Pm-147 or 2 x 1011 Bq H-3 |
| A Ba-137m eluting source | 4 x 104 Bq Cs-137+ | 4 x 105 Bq Cs-137+ |
| A substance or article which is or contains magnesium alloy or thoriated tungsten in which the thorium concentration does not exceed 4% by mass | No limit | No limit |
| A uranium or thorium compound | Up to a total of 5kg of uranium and thorium | Up to a total of 5kg of uranium and thorium |
| A substance or article (other than a sealed source) which is intended for use for, used for, or arises from medical or veterinary diagnosis or treatment or clinical or veterinary trials | 1 x 109 Bq Tc-99m | 1 x 109 Bq Tc-99m |
| and | and | |
| in respect of the total for all other radionuclides— | 2 x 108 Bq of all other radionuclides, (no more than 1 x 108 Bq of which is contained in radioactive material) | |
| (i) 1 x 108 Bq if the substance or article is radioactive material, or | ||
| (ii) 2 x 108 Bq if the substance or article is radioactive waste |
26.—(1) The Table 5 referred to in Sections 2 and 4 of this Part is—
| Radionuclides | Maximum quantity of radioactivity (Bq) on any premises | Maximum concentration (Bq/g) |
|---|---|---|
| H-3 | 109 | 106 |
| Be-7 | 107 | 103 |
| C-14 | 107 | 104 |
| O-15 | 109 | 102 |
| F-18 | 106 | 10 |
| Na-22 | 106 | 10 |
| Na-24 | 105 | 10 |
| Si-31 | 106 | 103 |
| P-32 | 105 | 103 |
| P-33 | 108 | 105 |
| S-35 | 108 | 105 |
| Cl-36 | 106 | 104 |
| Cl-38 | 105 | 10 |
| Ar-37 | 108 | 106 |
| Ar-41 | 109 | 102 |
| K-42 | 106 | 102 |
| K-43 | 106 | 10 |
| Ca-45 | 107 | 104 |
| Ca-47 | 106 | 10 |
| Sc-46 | 106 | 10 |
| Sc-47 | 106 | 102 |
| Sc-48 | 105 | 10 |
| V-48 | 105 | 10 |
| Cr-51 | 107 | 103 |
| Mn-51 | 105 | 10 |
| Mn-52 | 105 | 10 |
| Mn-52m | 105 | 10 |
| Mn-53 | 109 | 104 |
| Mn-54 | 106 | 10 |
| Mn-56 | 105 | 10 |
| Fe-52 | 106 | 10 |
| Fe-55 | 106 | 104 |
| Fe-59 | 106 | 10 |
| Co-55 | 106 | 10 |
| Co-56 | 105 | 10 |
| Co-57 | 106 | 102 |
| Co-58 | 106 | 10 |
| Co-58m | 107 | 104 |
| Co-60 | 105 | 10 |
| Co-60m | 106 | 103 |
| Co-61 | 106 | 102 |
| Co-62m | 105 | 10 |
| Ni-59 | 108 | 104 |
| Ni-63 | 108 | 105 |
| Ni-65 | 106 | 10 |
| Cu-64 | 106 | 102 |
| Zn-65 | 106 | 10 |
| Zn-69 | 106 | 104 |
| Zn-69m | 106 | 102 |
| Ga-72 | 105 | 10 |
| Ge-71 | 108 | 104 |
| As-73 | 107 | 103 |
| As-74 | 106 | 10 |
| As-76 | 105 | 102 |
| As-77 | 106 | 103 |
| Se-75 | 106 | 102 |
| Br-82 | 106 | 10 |
| Kr-74 | 109 | 102 |
| Kr-76 | 109 | 102 |
| Kr-77 | 109 | 102 |
| Kr-79 | 105 | 103 |
| Kr-81 | 107 | 104 |
| Kr-83m | 1012 | 105 |
| Kr-85 | 104 | 105 |
| Kr-85m | 1010 | 103 |
| Kr-87 | 109 | 102 |
| Kr-88 | 109 | 102 |
| Rb-86 | 105 | 102 |
| Sr-85 | 106 | 102 |
| Sr-85m | 107 | 102 |
| Sr-87m | 106 | 102 |
| Sr-89 | 106 | 103 |
| Sr-90+ | 104 | 102 |
| Sr-91 | 105 | 10 |
| Sr-92 | 106 | 10 |
| Y-90 | 105 | 103 |
| Y-91 | 106 | 103 |
| Y-91m | 106 | 102 |
| Y-92 | 105 | 102 |
| Y-93 | 105 | 102 |
| Zr-93+ | 107 | 103 |
| Zr-95 | 106 | 10 |
| Zr-97+ | 105 | 10 |
| Nb-93m | 107 | 104 |
| Nb-94 | 106 | 10 |
| Nb-95 | 106 | 10 |
| Nb-97 | 106 | 10 |
| Nb-98 | 105 | 10 |
| Mo-90 | 106 | 10 |
| Mo-93 | 108 | 103 |
| Mo-99 | 106 | 102 |
| Mo-101 | 106 | 10 |
| Tc-96 | 106 | 10 |
| Tc-96m | 107 | 103 |
| Tc-97 | 108 | 103 |
| Tc-97m | 107 | 103 |
| Tc-99 | 107 | 104 |
| Tc-99m | 107 | 102 |
| Ru-97 | 107 | 102 |
| Ru-103 | 106 | 102 |
| Ru-105 | 106 | 10 |
| Ru-106+ | 105 | 102 |
| Rh-103m | 108 | 104 |
| Rh-105 | 107 | 102 |
| Pd-103 | 108 | 103 |
| Pd-109 | 106 | 103 |
| Ag-105 | 106 | 102 |
| Ag-108m+ | 106 | 10 |
| Ag-110m | 106 | 10 |
| Ag-111 | 106 | 103 |
| Cd-109 | 106 | 104 |
| Cd-115 | 106 | 102 |
| Cd-115m | 106 | 103 |
| In-111 | 106 | 102 |
| In-113m | 106 | 102 |
| In-114m | 106 | 102 |
| In-115m | 106 | 102 |
| Sn-113 | 107 | 103 |
| Sn-125 | 105 | 102 |
| Sb-122 | 104 | 102 |
| Sb-124 | 106 | 10 |
| Sb-125 | 106 | 102 |
| Te-123m | 107 | 102 |
| Te-125m | 107 | 103 |
| Te-127 | 106 | 103 |
| Te-127m | 107 | 103 |
| Te-129 | 106 | 102 |
| Te-129m | 106 | 103 |
| Te-131 | 105 | 102 |
| Te-131m | 106 | 10 |
| Te-132 | 107 | 102 |
| Te-133 | 105 | 10 |
| Te-133m | 105 | 10 |
| Te-134 | 106 | 10 |
| I-123 | 107 | 102 |
| I-125 | 106 | 103 |
| I-126 | 106 | 102 |
| I-129 | 105 | 102 |
| I-130 | 106 | 10 |
| I-131 | 106 | 102 |
| I-132 | 105 | 10 |
| I-133 | 106 | 10 |
| I-134 | 105 | 10 |
| I-135 | 106 | 10 |
| Xe-131m | 104 | 104 |
| Xe-133 | 104 | 103 |
| Xe-135 | 1010 | 103 |
| Cs-129 | 105 | 102 |
| Cs-131 | 106 | 103 |
| Cs-132 | 105 | 10 |
| Cs-134m | 105 | 103 |
| Cs-134 | 104 | 10 |
| Cs-135 | 107 | 104 |
| Cs-136 | 105 | 10 |
| Cs-137+ | 104 | 10 |
| Cs-138 | 104 | 10 |
| Ba-131 | 106 | 102 |
| Ba-140+ | 105 | 10 |
| La-140 | 105 | 10 |
| Ce-139 | 106 | 102 |
| Ce-141 | 107 | 102 |
| Ce-143 | 106 | 102 |
| Ce-144+ | 105 | 102 |
| Pr-142 | 105 | 102 |
| Pr-143 | 106 | 104 |
| Nd-147 | 106 | 102 |
| Nd-149 | 106 | 102 |
| Pm-147 | 107 | 104 |
| Pm-149 | 106 | 103 |
| Sm-151 | 108 | 104 |
| Sm-153 | 106 | 102 |
| Eu-152 | 106 | 10 |
| Eu-152m | 106 | 102 |
| Eu-154 | 106 | 10 |
| Eu-155 | 107 | 102 |
| Gd-153 | 107 | 102 |
| Gd-159 | 106 | 103 |
| Tb-160 | 106 | 10 |
| Dy-165 | 106 | 103 |
| Dy-166 | 106 | 103 |
| Ho-166 | 105 | 103 |
| Er-169 | 107 | 104 |
| Er-171 | 106 | 102 |
| Tm-170 | 106 | 103 |
| Tm-171 | 108 | 104 |
| Yb-175 | 107 | 103 |
| Lu-177 | 107 | 103 |
| Hf-181 | 106 | 10 |
| Ta-182 | 104 | 10 |
| W-181 | 107 | 103 |
| W-185 | 107 | 104 |
| W-187 | 106 | 102 |
| Re-186 | 106 | 103 |
| Re-188 | 105 | 102 |
| Os-185 | 106 | 10 |
| Os-191 | 107 | 102 |
| Os-191m | 107 | 103 |
| Os-193 | 106 | 102 |
| Ir-190 | 106 | 10 |
| Ir-192 | 104 | 10 |
| Ir-194 | 105 | 102 |
| Pt-191 | 106 | 102 |
| Pt-193m | 107 | 103 |
| Pt-197 | 106 | 103 |
| Pt-197m | 106 | 102 |
| Au-198 | 106 | 102 |
| Au-199 | 106 | 102 |
| Hg-197 | 107 | 102 |
| Hg-197m | 106 | 102 |
| Hg-203 | 105 | 102 |
| Tl-200 | 106 | 10 |
| Tl-201 | 106 | 102 |
| Tl-202 | 106 | 102 |
| Tl-204 | 104 | 104 |
| Pb-203 | 106 | 102 |
| Pb-210+ | 104 | 10 |
| Pb-212+ | 105 | 10 |
| Bi-206 | 105 | 10 |
| Bi-207 | 106 | 10 |
| Bi-210 | 106 | 103 |
| Bi-212+ | 105 | 10 |
| Po-203 | 106 | 10 |
| Po-205 | 106 | 10 |
| Po-207 | 106 | 10 |
| Po-210 | 104 | 10 |
| At-211 | 107 | 103 |
| Rn-220+ | 107 | 104 |
| Rn-222+ | 108 | 10 |
| Ra-223+ | 105 | 102 |
| Ra-224+ | 105 | 10 |
| Ra-225 | 105 | 102 |
| Ra-226+ | 104 | 10 |
| Ra-227 | 106 | 102 |
| Ra-228+ | 105 | 10 |
| Ac-228 | 106 | 10 |
| Th-226+ | 107 | 103 |
| Th-227 | 104 | 10 |
| Th-228+ | 104 | 1 |
| Th-229+ | 103 | 1 |
| Th-230 | 104 | 1 |
| Th-231 | 107 | 103 |
| Th-232 sec | 103 | 1 |
| Th-234+ | 105 | 103 |
| Pa-230 | 106 | 10 |
| Pa-231 | 103 | 1 |
| Pa-233 | 107 | 102 |
| U-230+ | 105 | 10 |
| U-231 | 107 | 102 |
| U-232+ | 103 | 1 |
| U-233 | 104 | 10 |
| U-234 | 104 | 10 |
| U-235+ | 104 | 10 |
| U-236 | 104 | 10 |
| U-237 | 106 | 102 |
| U-238+ | 104 | 10 |
| U-238 sec | 103 | 1 |
| U-239 | 106 | 102 |
| U-240 | 107 | 103 |
| U-240+ | 106 | 10 |
| Np-237+ | 103 | 1 |
| Np-239 | 107 | 102 |
| Np-240 | 106 | 10 |
| Pu-234 | 107 | 102 |
| Pu-235 | 107 | 102 |
| Pu-236 | 104 | 10 |
| Pu-237 | 107 | 103 |
| Pu-238 | 104 | 1 |
| Pu-239 | 104 | 1 |
| Pu-240 | 103 | 1 |
| Pu-241 | 105 | 102 |
| Pu-242 | 104 | 1 |
| Pu-243 | 107 | 103 |
| Pu-244 | 104 | 1 |
| Am-241 | 104 | 1 |
| Am-242 | 106 | 103 |
| Am-242m+ | 104 | 1 |
| Am-243+ | 103 | 1 |
| Cm-242 | 105 | 102 |
| Cm-243 | 104 | 1 |
| Cm-244 | 104 | 10 |
| Cm-245 | 103 | 1 |
| Cm-246 | 103 | 1 |
| Cm-247 | 104 | 1 |
| Cm-248 | 103 | 1 |
| Bk-249 | 106 | 103 |
| Cf-246 | 106 | 103 |
| Cf-248 | 104 | 10 |
| Cf-249 | 103 | 1 |
| Cf-250 | 104 | 10 |
| Cf-251 | 103 | 1 |
| Cf-252 | 104 | 10 |
| Cf-253 | 105 | 102 |
| Cf-254 | 103 | 1 |
| Es-253 | 105 | 102 |
| Es-254 | 104 | 10 |
| Es-254m | 106 | 102 |
| Fm-254 | 107 | 104 |
| Fm-255 | 106 | 103 |
| Any other radionuclide that is: | 103, or the quantity given in respect of that radionuclide in the Health Protection Agency's publication ‘Exempt Concentrations and Quantities for Radionuclides not Included in the European Basic Safety Standards Directive’M3. | 1, or the concentration given in respect of that radionuclide in the publication referenced in column 2. |
| (a) not of natural terrestrial or cosmic origin, or | ||
| (b) listed in Table 2 in this Schedule. |
(2) The summation rule in respect of column 2 of Table 5 is the sum of the quotients A/B where—
(a)“A” means the quantity of each radionuclide listed in column 1 of Table 5 that is present in the material and waste, and
(b)“B” means the quantity of that radionuclide specified in column 2 of Table 5.
(3) The summation rule in respect of column 2 of Table 5 is the sum of the quotients C/D where—
(a)“C” means the concentration of each radionuclide listed in column 1 of Table 5 that is present in the material and waste, and
(b)“D” means the concentration of that radionuclide specified in column 3 of Table 5.
Marginal Citations
M3Published by the National Radiological Protection Board, Chilton, Oxfordshire, 1999, NRPB-R306 (ISBN 978-0-85951-429-3). A copy may be obtained from the CRCE Directors' Office, Centre for Chemical, Radiation and Environmental Hazards, Public Health England, Chilton, Didcot, OX11 0RQ.
27. The Table 6 referred to in Sections 5 and 7 of this Part is—
| Radioactive waste | Maximum concentration of radionuclides | Maximum quantity of radioactivity to be disposed of in the period stated |
|---|---|---|
| Solid radioactive waste, with no single item > 4 x 104 Bq | 4 x 105 Bq for the sum of all radionuclides per 0.1m3 | 2 x 108 Bq/year |
| Solid radioactive waste containing tritium and C-14 only, with no single item > 4 x 105 Bq | 4 x 106 Bq of tritium and C-14 per 0.1m3 | 2 x 109 Bq/year |
| Individual sealed sources | 2 x 105 Bq for the sum of all radionuclides per 0.1m3 | 1 x 107 Bq/year |
| Individual sealed sources which are solely radioactive waste because they contain tritium | 2 x 1010 Bq of tritium per 0.1m3 | 1 x 1013 Bq/year |
| Luminised articles with no single item containing > 8 x 107 Bq of Pm-147 or > 4 x 109 of tritium | 8 x 107 Bq per 0.1m3 of Pm-147 | 2 x 109 Bq/year of Pm-147 |
| or 4 x 109 Bq per 0.1m3 for tritium | or 1 x 1011 Bq/year of tritium | |
| Solid radioactive waste which consists of magnesium alloy, thoriated tungsten or dross from hardener alloy in which the thorium concentration does not exceed 4% by mass | No limit | No limit |
| Solid uranium or thorium compound | No limit | 0.5kg of uranium or thorium per week |
| Aqueous liquid uranium or thorium compound | No limit | 0.5kg of uranium or thorium per year |
| Aqueous liquid human excreta | No limit | 1 x 1010 Bq/year of Tc-99m |
| and | ||
| 5 x 109 Bq/year for the sum of all other radionuclides |
28.—(1) The Table 7 referred to in Section 7 of this Part is—
| Radionuclide | Concentration in Bq/ litre | Maximum annual quantity of radionuclides to a relevant sewer (Bq/ year) | Maximum annual quantity of radionuclides directly into a relevant river or the sea (Bq/ year) |
|---|---|---|---|
| H-3 | 103 | 1010 | 1010 |
| Be-7 | 1 | 107 | 107 |
| C-14 | 0.1 | 106 | 106 |
| F-18 | 0.1 | 106 | 106 |
| Na-22 | 1 | 106 | 107 |
| Na-24 | 1 | 107 | 107 |
| Si-31 | 10 | 108 | 108 |
| P-32 | 0.001 | 104 | 104 |
| P-33 | 0.001 | 104 | 104 |
| S-35 | 10 | 3 x 107 | 108 |
| Cl-36 | 10 | 107 | 108 |
| Cl-38 | 0.1 | 106 | 106 |
| K-42 | 0.01 | 105 | 105 |
| K-43 | 0.01 | 105 | 105 |
| Ca-45 | 1 | 107 | 107 |
| Ca-47 | 0.1 | 106 | 106 |
| Sc-46 | 0.001 | 104 | 104 |
| Sc-47 | 0.01 | 105 | 105 |
| Sc-48 | 0.001 | 104 | 104 |
| V-48 | 1 | 107 | 107 |
| Cr-51 | 10 | 108 | 108 |
| Mn-51 | 0.001 | 104 | 104 |
| Mn-52 | 0.001 | 104 | 104 |
| Mn-52m | 0.001 | 104 | 104 |
| Mn-53 | 1 | 107 | 107 |
| Mn-54 | 0.01 | 105 | 105 |
| Mn-56 | 0.001 | 104 | 104 |
| Fe-52 | 0.01 | 105 | 105 |
| Fe-55 | 1 | 107 | 107 |
| Fe-59 | 0.01 | 105 | 105 |
| Co-55 | 0.001 | 104 | 104 |
| Co-56 | 0.001 | 104 | 104 |
| Co-57 | 0.1 | 106 | 106 |
| Co-58 | 0.1 | 106 | 106 |
| Co-58m | 1 | 107 | 107 |
| Co-60 | 0.01 | 105 | 105 |
| Co-60m | 1 | 107 | 107 |
| Co-61 | 0.1 | 106 | 106 |
| Co-62m | 0.001 | 104 | 104 |
| Ni-59 | 1 | 107 | 107 |
| Ni-63 | 102 | 109 | 109 |
| Ni-65 | 0.01 | 105 | 105 |
| Cu-64 | 0.1 | 106 | 106 |
| Zn-65 | 0.1 | 3 x 105 | 106 |
| Zn-69 | 10 | 108 | 108 |
| Zn-69m | 0.1 | 106 | 106 |
| Ga-67 | 0.1 | 106 | 106 |
| Ga-72 | 0.001 | 104 | 104 |
| Ge-71 | 1 | 107 | 107 |
| As-73 | 10 | 108 | 108 |
| As-74 | 1 | 107 | 107 |
| As-76 | 1 | 107 | 107 |
| As-77 | 1 | 107 | 107 |
| Se-75 | 0.1 | 3 x 105 | 106 |
| Br-82 | 0.1 | 106 | 106 |
| Rb-86 | 0.1 | 106 | 106 |
| Sr-85 | 0.1 | 106 | 106 |
| Sr-85m | 0.1 | 106 | 106 |
| Sr-87m | 0.1 | 106 | 106 |
| Sr-89 | 1 | 107 | 107 |
| Sr-90+ | 0.1 | 3 x 105 | 106 |
| Sr-91 | 0.01 | 105 | 105 |
| Sr-92 | 0.01 | 105 | 105 |
| Y-90 | 1 | 107 | 107 |
| Y-91 | 1 | 107 | 107 |
| Y-91m | 0.01 | 105 | 105 |
| Y-92 | 0.1 | 106 | 106 |
| Y-93 | 0.1 | 106 | 106 |
| Zr-93 | 10 | 108 | 108 |
| Zr-95+ | 0.001 | 104 | 104 |
| Zr-97 | 0.01 | 105 | 105 |
| Nb-93m | 10 | 108 | 108 |
| Nb-94 | 0.1 | 106 | 106 |
| Nb-95 | 1 | 107 | 107 |
| Nb-97 | 1 | 107 | 107 |
| Nb-98 | 0.1 | 106 | 106 |
| Mo-90 | 0.1 | 106 | 106 |
| Mo-93 | 1 | 107 | 107 |
| Mo-99 | 0.1 | 106 | 106 |
| Mo-101 | 0.01 | 105 | 105 |
| Tc-96 | 1 | 107 | 107 |
| Tc-96m | 102 | 109 | 109 |
| Tc-97 | 102 | 109 | 109 |
| Tc-97m | 10 | 108 | 108 |
| Tc-99 | 10 | 107 | 108 |
| Tc-99m | 10 | 3 x 107 | 108 |
| Ru-97 | 0.01 | 105 | 105 |
| Ru-103 | 0.01 | 105 | 105 |
| Ru-105 | 0.01 | 105 | 105 |
| Ru-106+ | 0.1 | 106 | 106 |
| Rh-103m | 10 | 108 | 108 |
| Rh-105 | 1 | 107 | 107 |
| Pd-103 | 0.1 | 106 | 106 |
| Pd-109 | 0.1 | 106 | 106 |
| Ag-105 | 1 | 107 | 107 |
| Ag-108m | 0.1 | 106 | 106 |
| Ag-110m | 0.1 | 106 | 106 |
| Ag-111 | 10 | 108 | 108 |
| Cd-109 | 1 | 107 | 107 |
| Cd-115 | 0.1 | 106 | 106 |
| Cd-115m | 1 | 107 | 107 |
| In-111 | 0.01 | 105 | 105 |
| In-113m | 0.01 | 105 | 105 |
| In-114m | 0.01 | 105 | 105 |
| In-115m | 0.01 | 105 | 105 |
| Sn-113 | 0.1 | 106 | 106 |
| Sn-125 | 0.01 | 105 | 105 |
| Sb-122 | 0.1 | 106 | 106 |
| Sb-124 | 0.1 | 106 | 106 |
| Sb-125 | 1 | 107 | 107 |
| Te-123m | 1 | 107 | 107 |
| Te-125m | 1 | 107 | 107 |
| Te-127 | 10 | 108 | 108 |
| Te-127m | 1 | 107 | 107 |
| Te-129 | 10 | 108 | 108 |
| Te-129m | 1 | 107 | 107 |
| Te-131 | 1 | 107 | 107 |
| Te-131m | 1 | 107 | 107 |
| Te-132 | 0.1 | 106 | 106 |
| Te-133 | 1 | 107 | 107 |
| Te-133m | 1 | 107 | 107 |
| Te-134 | 1 | 107 | 107 |
| I-123 | 1 | 107 | 107 |
| I-125 | 1 | 107 | 107 |
| I-126 | 0.1 | 106 | 106 |
| I-129 | 0.1 | 106 | 106 |
| I-130 | 0.1 | 106 | 106 |
| I-131 | 0.1 | 106 | 106 |
| I-132 | 0.1 | 106 | 106 |
| I-133 | 0.1 | 106 | 106 |
| I-134 | 0.1 | 106 | 106 |
| I-135 | 0.1 | 106 | 106 |
| Cs-129 | 0.01 | 105 | 105 |
| Cs-131 | 0.1 | 106 | 106 |
| Cs-132 | 0.01 | 105 | 105 |
| Cs-134 | 0.01 | 105 | 105 |
| Cs-134m | 0.1 | 106 | 106 |
| Cs-135 | 0.1 | 106 | 106 |
| Cs-136 | 0.001 | 104 | 104 |
| Cs-137+ | 0.01 | 105 | 105 |
| Cs-138 | 0.001 | 104 | 104 |
| Ba-131 | 0.1 | 106 | 106 |
| Ba-140 | 0.1 | 106 | 106 |
| La-140 | 0.001 | 104 | 104 |
| Ce-139 | 0.1 | 106 | 106 |
| Ce-141 | 0.1 | 106 | 106 |
| Ce-143 | 0.01 | 105 | 105 |
| Ce-144 | 0.1 | 106 | 106 |
| Pr-142 | 0.1 | 106 | 106 |
| Pr-143 | 10 | 108 | 108 |
| Nd-147 | 0.01 | 105 | 105 |
| Nd-149 | 0.01 | 105 | 105 |
| Pm-147 | 10 | 108 | 108 |
| Pm-149 | 1 | 107 | 107 |
| Sm-151 | 102 | 109 | 109 |
| Sm-153 | 0.1 | 106 | 106 |
| Eu-152 | 0.01 | 105 | 105 |
| Eu-152m | 0.01 | 105 | 105 |
| Eu-154 | 0.01 | 105 | 105 |
| Eu-155 | 0.1 | 106 | 106 |
| Gd-153 | 0.1 | 106 | 106 |
| Gd-159 | 0.1 | 106 | 106 |
| Tb-160 | 0.01 | 105 | 105 |
| Dy-165 | 0.1 | 106 | 106 |
| Dy-166 | 0.1 | 106 | 106 |
| Ho-166 | 0.1 | 106 | 106 |
| Er-169 | 10 | 108 | 108 |
| Er-171 | 0.01 | 105 | 105 |
| Tm-170 | 1 | 107 | 107 |
| Tm-171 | 10 | 108 | 108 |
| Yb-175 | 0.1 | 106 | 106 |
| Lu-177 | 0.1 | 106 | 106 |
| Hf-181 | 0.01 | 105 | 105 |
| Ta-182 | 0.001 | 104 | 104 |
| W-181 | 0.1 | 106 | 106 |
| W-185 | 1 | 107 | 107 |
| W-187 | 0.01 | 105 | 105 |
| Re-186 | 1 | 107 | 107 |
| Re-188 | 1 | 107 | 107 |
| Os-185 | 0.01 | 105 | 105 |
| Os-191 | 0.1 | 106 | 106 |
| Os-191m | 1 | 107 | 107 |
| Os-193 | 0.1 | 106 | 106 |
| Ir-190 | 0.001 | 104 | 104 |
| Ir-192 | 0.01 | 105 | 105 |
| Ir-194 | 0.1 | 106 | 106 |
| Pt-191 | 0.01 | 105 | 105 |
| Pt-193m | 1 | 107 | 107 |
| Pt-197 | 0.1 | 106 | 106 |
| Pt-197m | 0.1 | 106 | 106 |
| Au-198 | 1 | 107 | 107 |
| Au-199 | 1 | 107 | 107 |
| Hg-197 | 1 | 107 | 107 |
| Hg-197m | 0.1 | 106 | 106 |
| Hg-203 | 0.1 | 106 | 106 |
| Tl-200 | 0.01 | 105 | 105 |
| Tl-201 | 0.1 | 106 | 106 |
| Tl-202 | 0.01 | 105 | 105 |
| Tl-204 | 0.1 | 106 | 106 |
| Pb-203 | 0.01 | 105 | 105 |
| Pb-210 | 0.001 | 104 | 104 |
| Pb-212 | 0.1 | 106 | 106 |
| Bi-206 | 0.01 | 105 | 105 |
| Bi-207 | 0.1 | 106 | 106 |
| Bi-210 | 10 | 108 | 108 |
| Bi-212 | 1 | 107 | 107 |
| Po-203 | 0.001 | 104 | 104 |
| Po-205 | 0.001 | 104 | 104 |
| Po-207 | 0.001 | 104 | 104 |
| Po-210 | 0.001 | 104 | 104 |
| At-211 | 1 | 107 | 107 |
| Ra-223 | 0.01 | 105 | 105 |
| Ra-224+ | 0.01 | 105 | 105 |
| Ra-225 | 0.01 | 105 | 105 |
| Ra-226+ | 0.01 | 105 | 105 |
| Ra-227 | 1 | 107 | 107 |
| Ra-228 | 0.01 | 105 | 105 |
| Ac-227 | 0.1 | 106 | 106 |
| Ac-228 | 0.001 | 104 | 104 |
| Th-226 | 0.1 | 106 | 106 |
| Th-227 | 0.01 | 105 | 105 |
| Th-228 | 1 | 107 | 107 |
| Th-229 | 0.01 | 105 | 105 |
| Th-230 | 1 | 107 | 107 |
| Th-231 | 0.1 | 106 | 106 |
| Th-232 | 1 | 106 | 107 |
| Th-234 | 0.1 | 106 | 106 |
| Pa-230 | 0.01 | 105 | 105 |
| Pa-231 | 0.01 | 105 | 105 |
| Pa-233 | 0.1 | 106 | 106 |
| U-230 | 0.1 | 106 | 106 |
| U-231 | 10 | 108 | 108 |
| U-232 | 0.1 | 106 | 106 |
| U-233 | 0.1 | 106 | 106 |
| U-234 | 0.1 | 106 | 106 |
| U-235+ | 0.1 | 106 | 106 |
| U-236 | 0.1 | 106 | 106 |
| U-237 | 10 | 108 | 108 |
| U-238+ | 0.1 | 106 | 106 |
| U-239 | 10 | 108 | 108 |
| U-240 | 10 | 108 | 108 |
| Np-237 | 0.1 | 106 | 106 |
| Np-239 | 1 | 107 | 107 |
| Np-240 | 0.1 | 106 | 106 |
| Pu-234 | 0.01 | 105 | 105 |
| Pu-235 | 0.01 | 105 | 105 |
| Pu-236 | 1 | 107 | 107 |
| Pu-237 | 0.1 | 106 | 106 |
| Pu-238 | 0.1 | 106 | 106 |
| Pu-239 | 0.1 | 106 | 106 |
| Pu-240 | 0.1 | 106 | 106 |
| Pu-241 | 10 | 108 | 108 |
| Pu-242 | 0.1 | 106 | 106 |
| Pu-243 | 0.1 | 106 | 106 |
| Pu-244 | 0.1 | 106 | 106 |
| Am-241 | 0.1 | 106 | 106 |
| Am-242 | 0.1 | 106 | 106 |
| Am-242m | 0.1 | 106 | 106 |
| Am-243 | 0.1 | 106 | 106 |
| Cm-242 | 1 | 107 | 107 |
| Cm-243 | 0.1 | 106 | 106 |
| Cm-244 | 0.1 | 106 | 106 |
| Cm-245 | 0.01 | 105 | 105 |
| Cm-246 | 0.1 | 106 | 106 |
| Cm-247 | 0.01 | 105 | 105 |
| Cm-248 | 0.1 | 106 | 106 |
| Bk-249 | 102 | 109 | 109 |
| Cf-246 | 1 | 107 | 107 |
| Cf-248 | 1 | 107 | 107 |
| Cf-249 | 0.01 | 105 | 105 |
| Cf-250 | 0.1 | 106 | 106 |
| Cf-251 | 0.01 | 105 | 105 |
| Cf-252 | 0.1 | 106 | 106 |
| Cf-253 | 10 | 108 | 108 |
| Cf-254 | 0.0001 | 103 | 103 |
| Es-253 | 1 | 107 | 107 |
| Es-254 | 0.1 | 106 | 106 |
| Es-254m | 0.01 | 105 | 105 |
| Fm-254 | 1 | 107 | 107 |
| Fm-255 | 0.1 | 106 | 106 |
| Any other radionuclide that is not of natural terrestrial or cosmic origin | 0.0001 | 103 | 103 |
| or that concentration which gives rise to a dose to a member of the public of 10 microsieverts per year calculated in accordance with the methodology used to calculate other concentrations in this table M4. | or that quantity which corresponds to 3,000m3 of aqueous radioactive waste up to the appropriate concentration as calculated in accordance with column 2. | or that quantity which corresponds to 10,000m3 of aqueous radioactive waste up to the appropriate concentration as calculated in accordance with column 2. |
(2) The summation rule in respect of column 2 of Table 7 is the sum of the quotients A/B where—
(a)“A” means the concentration in Bq/ litre of each radionuclide listed in column 1 of Table 7 that is present in aqueous waste which is not described in a row in column 1 of Table 6, and
(b)“B” means the concentration of that radionuclide specified in column 2 of Table 7.
(3) The summation rule in respect of column 3 of Table 7 is the sum of the quotients C/D where—
(a)“C” means the quantity in Bq of each radionuclide listed in column 1 of Table 7 that is present in the aqueous waste which is not described in a row in column 1 of Table 6 which is disposed of in the year, and
(b)“D” means the quantity of that radionuclide specified in column 3 of Table 7.
(4) The summation rule in respect of column 4 of Table 7 is the sum of the quotients C/E where—
(a)“C” means the quantity in Bq of each radionuclide listed in column 1 of Table 7 that is present in the aqueous waste which is not described in a row in column 1 of Table 6 which is disposed of in the year, and
(b)“E” means the quantity of that radionuclide specified in column 4 of Table 7.
Marginal Citations
M4The concentrations in this table were calculated using methods adopted by the Health Protection Agency in their document HPA-CRCE-005 - Derivation of Liquid Exclusion or Exemption Levels to Support the RSA93 Exemption Order Review, published in Chilton, Oxfordshire in August 2010 (ISBN 0-978-85951-673-0).
29. In this Section, where any radionuclide carries the suffix “+” or “sec”—
(a)that radionuclide represents the parent radionuclide in secular equilibrium with the corresponding daughter radionuclides which are identified in column 2 of Table 8 adjacent to that parent radionuclide, and
(b)a concentration or activity value given in respect of such a parent radionuclide is the value for the parent radionuclide alone, but already takes into account the daughter radionuclides in column 2 that are present.
30. The Table 8 referred to in paragraph 29 is—
| Parent radionuclide | Daughter radionuclides |
|---|---|
| Sr-90+ | Y-90 |
| Zr-93+ | Nb-93m |
| Zr-95+ | Nb-95 |
| Zr-97+ | Nb-97 |
| Ru-106+ | Rh-106 |
| Ag-108m+ | Ag-108 |
| Cs-137+ | Ba-137m |
| Ba-140+ | La-140 |
| Ce-144+ | Pr-144 |
| Pb-210+ | Bi-210, Po-210 |
| Pb-212+ | Bi-212, Tl-208, Po-212 |
| Bi-212+ | Tl-208, Po-212 |
| Rn-220+ | Po-216 |
| Rn-222+ | Po-218, Pb-214, Bi-214, Po-214 |
| Ra-223+ | Rn-219, Po-215, Pb-211, Bi-211, Tl-207 |
| Ra-224+ | Where Ra-224+ is referred to in Table 5: Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 |
| Where Ra-224+ is referred to in Table 7: Pb-212 | |
| Ra-226+ | Where Ra-226+ is referred to in Table 5: Rn-222, Po-218, Pb-214, Bi-214, Pb-210, Bi-210, Po-210, Po-214 |
| Where Ra-226+ is referred to in Table 7: Rn-222, Po-218, Pb-214, Bi-214, Po-214 | |
| Ra-228+ | Ac-228 |
| Th-226+ | Ra-222, Rn-218, Po-214 |
| Th-228+ | Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Po-212, Tl-208 |
| Th-229+ | Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 |
| Th-232 sec | Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Po-212, Tl-208 |
| Th-234+ | Pa-234m |
| U-230+ | Th-226, Ra-222, Rn-218, Po-214 |
| U-232+ | Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 |
| U-235+ | Th-231 |
| U-238+ | Th-234, Pa-234m, Pa-234 |
| U-238 sec | Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Pb-210, Bi-210, Po-210, Po-214 |
| U-240+ | Np-240 |
| Np-237+ | Pa-233 |
| Am-242m+ | Am-242 |
| Am-243+ | Np-239 |