The Environmental Permitting (England and Wales) Regulations 2016

PART 6 Radioactive substances activity exemptions

SECTION 1 General

Interpretation

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—

(a)

in each sealed container in the device does not exceed 8 x 10¹⁰ Bq of tritium, and

(b)

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—

(a)

in a vessel or aircraft, or

(b)

in a vehicle or other equipment used or intended to be used by the armed forces of the Crown;

“disposal permit” means—

(a)

an environmental permit to carry on the radioactive substances activity described in paragraph 11(2)(b) of Part 2 of this Schedule, or

(b)

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—

(a)

incorporates tritium in one or more sealed containers constructed to prevent dispersion of that tritium in normal use, and

(b)

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—

(a)

is radioactive material or radioactive waste solely because it contains Pm-147 or H-3, and

(b)

is not a sealed source;

“management”, in respect of waste, means—

(a)

the preparation by checking, cleaning or repairing that waste for its re-use without further processing,

(b)

the recovery of that waste,

(c)

the disposal of that waste, or

(d)

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—

(a)

is not a part of the sea, and

(b)

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)

a public sewer, or

(b)

a disposal main which leads to a sewage disposal works that—

(i)

has the capacity to handle a minimum of 100m³ of effluent per day, and

(ii)

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(1);

“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—

(a)

has a mechanically tough surface into which tritium is incorporated, and

(b)

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—

(a)

U-235 in the uranium it contains is no more than 0.72% by mass, and

(b)

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—

(a)

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

(b)

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.

Interpretation: NORM

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(2) 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.

SECTION 2 Exemption for keeping and using radioactive material and accumulating radioactive waste

Exemption for keeping and using radioactive material

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.

Exemption for accumulating radioactive waste

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.

Radioactive substances exempted under paragraphs 3 and 4

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.

Conditions in respect of the total quantity or concentration of radioactive substances on any premises

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.

Exemption for accumulating NORM waste

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.

SECTION 3 Exemption for keeping or using mobile radioactive apparatus

Exemption for keeping or using mobile radioactive apparatus

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.

SECTION 4 Relevant standard conditions

Interpretation of this Section

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.

Relevant standard conditions

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.

General conditions

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.

Loss or theft conditions

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.

Loss or theft conditions: mobile radioactive apparatus

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.

Condition to dispose of accumulated waste

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.

SECTION 5 Exemption for disposing of solid radioactive waste

Exemption for receiving and disposing of solid radioactive waste

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).

Solid radioactive waste

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.

Conditions in respect of solid radioactive waste

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.

SECTION 6 Exemption for disposing of NORM waste

Exemption for receiving and disposing of NORM waste

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).

Conditions in respect of NORM waste

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.

SECTION 7 Exemption for disposing of aqueous radioactive waste

Exemption for disposing of aqueous radioactive waste in Table 6

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.

Exemption for disposing of other aqueous radioactive waste

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.

Conditions in respect of aqueous radioactive waste in paragraph 21

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.

SECTION 8 Exemption for disposal of gaseous radioactive waste

Exemption for disposal of gaseous radioactive waste

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.

Conditions in respect of gaseous radioactive waste

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.

SECTION 9 Tables and summation rules in this Part

Table 4

25.  The Table 4 referred to in Sections 2 and 3 of this Part—

Table 4

Radioactive material and accumulated radioactive waste: values of maximum quantities

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

Table 5

26.—(1) The Table 5 referred to in Sections 2 and 4 of this Part is—

Table 5

Radionuclides: values of quantities and concentrations

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’(3).	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.

Table 6

27.  The Table 6 referred to in Sections 5 and 7 of this Part is—

Table 6

Radioactive waste: values of quantities and concentrations

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

Table 7

28.—(1) The Table 7 referred to in Section 7 of this Part is—

Table 7

Aqueous radioactive waste values

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(4).	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.

Interpretation of this Section

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.

Table 8

30.  The Table 8 referred to in paragraph 29 is—

Table 8

Radionuclides in secular equilibrium

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

(1)

1991 c. 56; the definition of “public sewer” was amended by section 99(6) of the Water Act 2003 (c. 37).

(2)

1965 c. 57; section 1 was substituted by paragraph 17 of Part 2 of Schedule 12 to the Energy Act 2013 (c. 32).

(3)

Published 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.

(4)

The 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).