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The Environmental Authorisations (Scotland) Regulations 2018

Status:

This is the original version (as it was originally made).

Regulation 10

SCHEDULE 9GENERAL BINDING RULES

This schedule has no associated Policy Notes

PART 1General binding rules

Column 1Column 2
ActivityGeneral Binding Rules
1. The management of a category 5 sealed source.
(a)

The radioactive substances common rules;

(b)

a non-metallic category 5 sealed source must only be disposed of in normal refuse;

(c)

the activity of an individual category 5 sealed source disposed of must not exceed 2 × 105 becquerels;

(d)

more than one source must not be disposed of in any 0.1 m3 of normal refuse;

(e)

the total activity of category 5 sealed sources disposed of in normal refuse from premises in a year must not exceed 1 × 107 becquerels;

(f)

a metallic category 5 sealed source must only be disposed of by landfill.

2. The management of a smoke detector.
(a)

The total number of smoke detectors kept on a premises, and not affixed to the premises, must not exceed 500.

(b)

a smoke detector must be managed in a manner which prevents the dispersal of radionuclides;

(c)

a smoke detector must only be disposed of in normal refuse;

(d)

more than one smoke detector must not be disposed of in any 0.1 m3 of normal refuse.

3. The management of a tritium source.
(a)

The radioactive substances common rules;

(b)

the total activity of tritium sources, other than Class B gaseous tritium light devices and Class C gaseous tritium light devices, on a premises must not exceed 5 × 1012 becquerels;

(c)

the total activity of Class B gaseous tritium light devices and Class C gaseous tritium light devices on a premises must not exceed 3 × 1013 becquerels;

(d)

a tritium source with an activity greater than 2 × 1010 becquerels must not be disposed of;

(e)

a tritium source must only be disposed of in normal refuse;

(f)

more than one tritium source must not be disposed of in any 0.1 m3 of normal refuse;

(g)

the total activity of tritium sources disposed of in normal refuse from a premises in a year must not exceed 1 × 1013 becquerels.

4. The management (other than the disposal) of an electrodeposited source.
(a)

The radioactive substances common rules.

5. The management of a barium eluting source.
(a)

The radioactive substances common rules;

(b)

the total activity of all barium eluting sources kept on a premises must not exceed 4 × 105 becquerels of Cs-137+;

(c)

a waste barium eluting source must only be disposed of in normal refuse;

(d)

more than one barium eluting source must not be disposed of in any 0.1 m3 of normal refuse;

6. The management of a thorium alloy.
(a)

The radioactive substances common rules;

(b)

a thorium alloy must only be disposed of by landfill.

7. The management of a uranium or thorium compound.
(a)

The radioactive substances common rules;

(b)

a uranium or thorium compound which is solid waste must only be disposed of in normal refuse;

(c)

the total quantity of uranium or thorium in a uranium or thorium compound disposed of from a premises in normal refuse must not exceed 0.5 kilogrammes per week;

(d)

a uranium or thorium compound which is aqueous waste must be disposed of to a relevant sewer;

(e)

the total quantity of uranium or thorium in a uranium or thorium compound disposed of from a premises to a relevant sewer must not exceed 0.5 kilogrammes per year.

8. The management of a medical or veterinary radioactive substance.
(a)

The radioactive substances common rules;

(b)

a medical or veterinary radioactive substance must only be—

(i)

disposed of in normal refuse; or

(ii)

disposed into—

(aa)

a relevant sewer;

(bb)

a river, which at the time of any disposal into it of aqueous radioactive waste has a flow rate which is not less than 1m3s-1; or

(cc)

the sea;

(c)

a single item of medical or veterinary radioactive waste must not be disposed of in normal refuse if its activity exceeds—

(i)

4 × 105 becquerels for tritium or C-14; or

(ii)

4 × 104 becquerels for any other radionuclide;

(d)

the total activity of medical or veterinary radioactive waste disposed of per 0.1 m3 of normal refuse must not exceed—

(i)

4 × 106 becquerels for tritium or C-14; or

(ii)

4 × 105 becquerels for any other radionuclide;

(e)

the total activity of medical or veterinary waste disposed of in normal refuse from a premises in a year must not exceed—

(i)

2 × 109 becquerels for tritium or C-14; or

(ii)

2 x 108 becquerels for any other radionuclide;

(f)

if the medical or veterinary waste consists of human excreta, the total activity of liquid aqueous waste disposed of from a premises to a relevant sewer in a year must not exceed—

(i)

1 x 1010 becquerels for Tc-99m; or

(ii)

5 x 109 becquerels for the sum of all other radionuclides;

(g)

if the medical or veterinary waste does not consist of human excreta, the total activity of liquid aqueous waste disposed of from a premises to a relevant sewer in a year must not exceed—

(i)

1 x 108 becquerels 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; or

(ii)

1 x 106 becquerels for the sum of all other radionuclides;

(h)

if the waste does not consist of human excreta, the concentration of liquid aqueous waste disposed of from a premises to a relevant sewer must not exceed 100 becquerels per millilitre.

9. The management (other than disposal) of a NORM containing substance.
(a)

The radioactive substances common rules;

(b)

the total activity of NORM containing substances transferred from a premises in a year to a person for disposal in a landfill must not exceed the value specified in column 3 of Table 1;

(c)

the total activity of NORM containing substances transferred from a premises in a year to a person for incineration must not exceed the value specified in column 4 of Table 1.

10. The disposal of gaseous radioactive waste which—
(a)

The total amount of gaseous Kr-85 waste disposed of from premises in a year must not exceed 1 × 1011 becquerels;

(b)

gaseous Kr-85 waste must be adequately dispersed from the building in which it arose so that it does not enter, or re-enter, a building.

(a)

contains no radionuclides other than Kr-85; and

(b)

arises from lamps containing Kr-85.

11. Any other radioactive substances activity, not falling within any other activity description in this schedule, where—
(a)

The radioactive substances common rules;

(a)

the total activity of a radionuclide does not exceed the value specified in column 2 of Table 2; or

(b)

a solid radioactive substance must only be disposed of in normal refuse;

(b)

the concentration of radioactivity of a radionuclide does not exceed the value specified in column 3 of Table 2.

(c)

a single item of radioactive waste must not be disposed of in normal refuse if it exceeds—

(i)

4 × 105 becquerels for tritium or C-14; or

(ii)

4 × 104 becquerels for any other radionuclide;

(d)

the total activity of radioactive substances disposed of per 0.1 m3 of normal refuse must not exceed—

(i)

4 × 106 becquerels for tritium or C-14; or

(ii)

4 × 105 becquerels for any other radionuclide;

(e)

an aqueous liquid radioactive substance must only be disposed of into—

(i)

a relevant sewer;

(ii)

a river, which at the time of any disposal into it of aqueous radioactive waste has a flow rate which is not less than 1m3s-1; or

(iii)

the sea;

(f)

the total activity of liquid aqueous radioactive waste disposed of from a premises in a year must not exceed—

(i)

1 x 108 becquerels 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, T1-201; or

(ii)

1 x 106 becquerels for the sum of all other radionuclides;

(g)

the concentration of liquid aqueous radioactive waste disposed of from a premises must not exceed 100 becquerels per millilitre;

(h)

gaseous waste must not be disposed of unless—

(i)

it consists of fugitive releases from a container; and

(ii)

it is dispersed from a building in such a way that it does not enter or re-enter a building.

PART 2Interpretation of general binding rules

1.  In this schedule—

“barium eluting source” means a source which—

(a)

consists of Cs-137+ in a sealed container which is designed and constructed to allow the elution of Ba-137m;

(b)

is radioactive material or radioactive waste solely because of that Cs-137+; and

(c)

does not contain an activity exceeding 4 × 104 becquerels of Cs-137+;

“category 5 sealed source” means a source, or an aggregate of sources, that would fall within category 5 as defined by the International Atomic Energy Agency in Categorisation of Radioactive Sources (RS-G-1.9)(1);

“Class A gaseous tritium light device” means such a device where the activity of the device does not exceed 2 × 1010 becquerels of tritium;

“Class B gaseous tritium light device” means such a 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 × 1010 becquerels of tritium; and

(b)

of the device does not exceed 1 × 1012 becquerels of tritium;

“Class C gaseous tritium light device” means such a 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;

“disposed of in normal refuse” means disposed of with substantial quantities of non-radioactive waste for landfill or incineration or composting where the radioactive waste will be mixed with such non-radioactive waste for the purposes of such burial, incineration or recovery;

“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 the total activity of which does not exceed—

(a)

6 × 108 becquerels of Ni-63; or

(b)

2 × 108 becquerels of Fe-55;

“gaseous tritium light device” means a sealed source (or such a source which has become broken) which incorporates tritium in a device which is an illuminant, instrument, sign or indicator;

“luminised article” means an article other than a sealed source—

(a)

which is made wholly or partly from a luminescent substance in the form of a film or a paint;

(b)

the activity of which does not exceed 4 × 109 becquerels;

“manage” means any activity involving radioactive material or radioactive waste except the production of radionuclides or the manufacture of radioactive sources and related expressions are to be construed accordingly;

“medical or veterinary radioactive substance” means radioactive material or radioactive waste (other than a sealed source) which is intended for use, is used, or arises from medical or veterinary diagnosis or treatment or clinical or veterinary trials;

“relevant sewer” means—

(a)

a public sewer; or

(b)

a private sewer which leads to a sewage treatment works that—

(i)

has the capacity to handle a minimum of 100m3 of sewage per day; and

(ii)

discharges treated sewage only to the sea, to a tidal estuary or to a river that has a flow rate of not less than 1m3s-1;

“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 in which the radioactive substance is permanently sealed in a capsule or incorporated in a solid form with the objective of preventing, under normal conditions of use, any dispersion of radioactive substances;

“sewer”, “public sewer”, “private sewer”, “sewage treatment works” and “sewage” have the same meanings as in section 59(1) of the Sewerage (Scotland) Act 1968(2);

“smoke detector” means a smoke detector incorporating a sealed source the total activity of which does not exceed 4 × 104 becquerels;

“Table 1” and “Table 2” mean the tables with that number in Part 3;

“thorium alloy” means a substance or article which is, or contains—

(a)

magnesium alloy;

(b)

thoriated tungsten; or

(c)

dross from hardener alloy,

in which the thorium content does not exceed 4% by mass;

“a tritium foil source” means an article which has a mechanically tough surface into which tritium is incorporated the total activity of which does not exceed 2 × 1010 becquerels;

“tritium source” means radioactive material or radioactive waste which contains no radionuclides except for tritium and which is either—

(a)

a gaseous tritium light device;

(b)

a sealed source;

(c)

a tritium foil source; or

(d)

a luminised article;

“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.

Interpretation: NORM

2.—(1) In this schedule, “NORM containing substance” means a solid substance or article which—

(a)is either—

(i)radioactive material or radioactive waste under paragraph 6(2) of schedule 8; or

(ii)except where sub-paragraph (2) applies, radioactive waste under paragraph 7 of schedule 8 arising from the remediation of land contaminated by radium;

(b)contains one or more of the radionuclides which are listed in column 1 of Table 1; and

(c)has a concentration of radioactivity that does not exceed the value specified in column 2 of Table 2 in respect of that radionuclide.

(2) Land is not contaminated under sub-paragraph (1)(a)(ii) unless the contamination occurred prior to 13th May 2000.

Interpretation: radioactive substances common rules

3.  In this schedule, “radioactive substances common rules” means the following rules—

(a)a radioactive substance must be managed in a manner which prevents the reckless or accidental dispersal of radionuclides and, in the case of a sealed source, which prevents any dispersal of radionuclides;

(b)a radioactive substance must be managed safely and securely to minimise the risk of—

(i)unauthorised or accidental use;

(ii)loss; and

(iii)theft;

(c)records of a radioactive substance must be kept—

(i)from receipt of a radioactive substance until at least 2 years after the date of its transfer or disposal;

(ii)which include, as a minimum, a description of each source, article or radioactive substance, the location where it is normally kept or used, details of any transfer, and details of any disposal;

(d)where practicable, a radioactive substance must be marked or labelled as radioactive but any labelling or marking must be removed before it is disposed of in normal refuse;

(e)SEPA must be promptly notified of a loss or theft (or suspected loss or theft) of radioactive substances where the total amount of radioactive substances lost or stolen (or suspected to have been lost or stolen) from the premises, together with the amount of other substances lost or stolen from the premises in the preceding 12 months, exceeds the value that is ten times the value for the relevant radionuclide in column 3 of Table 2;

(f)a radioactive substance must not be transferred to a person who is not legally entitled to manage it;

(g)a radioactive substance must be transferred or disposed of as soon as practicable after it becomes waste.

PART 3Tables

Table 1

NORM waste concentrations and maximum disposal quantities

Radionuclide

NORM concentration

(Bq/g)

NORM total activity for landfill

(GBq/year)

NORM total activity for incineration

(MBq/year)

U-238sec550100
U-238+550100
U-234550100
Th-230550100
Ra-226+550100
Pb-210+1001000100
Po-2101001000100
U-235sec550100
U-235+550100
Pa-231550100
Ac-227+550100
Th-232sec550100
Th-232550100
Ra-228+550100
Th-228+550100

The summation rule in respect of column 2 of Table 1 is the sum of the quotients A/B where—

(a)“A” means the concentration of each radionuclide listed in column 1 of Table 1 that is present in the radioactive waste; and

(b)“B” means the concentration of that radionuclide specified in column 2 of Table 1.

The summation rule in respect of columns 3 and 4 of Table 1 is the sum of the quotients C/D where—

(a)“C” means the quantity of each radionuclide listed in column 1 of Table 1 that is present in the radioactive waste; and

(b)“D” means the quantity of that radionuclide specified in column 3 or 4 (as appropriate) of Table 1.

Table 2

Table of radionuclide activity values

Radionuclide

Activity Concentration

(kilobecquerels per kilogram(1))

Activity (becquerels)
(1)

Potassium salts in quantities less than 1000kg are exempted.

(2)

National Radiological Protection Board, Didcot (United Kingdom) 1999.

H-31 × 1061 × 109
Be-71 × 1031 × 107
C-141 × 1041 × 107
O-151 × 1021 × 109
F-181 × 1011 × 106
Na-221 × 1011 × 106
Na-241 × 1011 × 105
Si-311 × 1031 × 106
P-321 × 1031 × 105
P-331 × 1051 × 108
S-351 × 1051 × 108
Cl-361 × 1041 × 106
Cl-381 × 1011 × 105
Ar-371 × 1061 × 108
Ar-411 × 1021 × 109
K-40(1)1 × 1021 × 106
K-421 × 1021 × 106
K-431 × 1011 × 106
Ca-451 × 1041 × 107
Ca-471 × 1011 × 106
Sc-461 × 1011 × 106
Sc-471 × 1021 × 106
Sc-481 × 1011 × 105
V-481 × 1011 × 105
Cr-511 × 1031 × 107
Mn-511 × 1011 × 105
Mn-521 × 1011 × 105
Mn-52m1 × 1011 × 105
Mn-531 × 1041 × 109
Mn-541 × 1011 × 106
Mn-561 × 1011 × 105
Fe-521 × 1011 × 106
Fe-551 × 1041 × 106
Fe-591 × 1011 × 106
Co-551 × 1011 × 106
Co-561 × 1011 × 105
Co-571 × 1021 × 106
Co-581 × 1011 × 106
Co-58m1 × 1041 × 107
Co-601 × 1011 × 105
Co-60m1 × 1031 × 106
Co-611 × 1021 × 106
Co-62m1 × 1011 × 105
Ni-591 × 1041 × 108
Ni-631 × 1051 × 108
Ni-651 × 1011 × 106
Cu-641 × 1021 × 106
Zn-651 × 1011 × 106
Zn-691 × 1041 × 106
Zn-69m1 × 1021 × 106
Ga-721 × 1011 × 105
Ge-711 × 1041 × 108
As-731 × 1031 × 107
As-741 × 1011 × 106
As-761 × 1021 × 105
As-771 × 1031 × 106
Se-751 × 1021 × 106
Br-821 × 1011 × 106
Kr-741 × 1021 × 109
Kr-761 × 1021 × 109
Kr-771 × 1021 × 109
Kr-791 × 1031 × 105
Kr-811 × 1041 × 107
Kr-83m1 × 1051 × 1012
Kr-851 × 1051 × 104
Kr-85m1 × 1031 × 1010
Kr-871 × 1021 × 109
Kr-881 × 1021 × 109
Rb-861 × 1021 × 105
Sr-851 × 1021 × 106
Sr-85m1 × 1021 × 107
Sr-87m1 × 1021 × 106
Sr-891 × 1031 × 106
Sr-90+1 × 1021 × 104
Sr-911 × 1011 × 105
Sr-921 × 1011 × 106
Y-901 × 1031 × 105
Y-911 × 1031 × 106
Y-91m1 × 1021 × 106
Y-921 × 1021 × 105
Y-931 × 1021 × 105
Zr-93+1 × 1031 × 107
Zr-951 × 1011 × 106
Zr-97+1 × 1011 × 105
Nb-93m1 × 1041 × 107
Nb-941 × 1011 × 106
Nb-951 × 1011 × 106
Nb-971 × 1011 × 106
Nb-981 × 1011 × 105
Mo-901 × 1011 × 106
Mo-931 × 1031 × 108
Mo-991 × 1021 × 106
Mo-1011 × 1011 × 106
Tc-961 × 1011 × 106
Tc-96m1 × 1031 × 107
Tc-971 × 1031 × 108
Tc-97m1 × 1031 × 107
Tc-991 × 1041 × 107
Tc-99m1 × 1021 × 107
Ru-971 × 1021 × 107
Ru-1031 × 1021 × 106
Ru-1051 × 1011 × 106
Ru-106+1 × 1021 × 105
Rh-103m1 × 1041 × 108
Rh-1051 × 1021 × 107
Pd-1031 × 1031 × 108
Pd-1091 × 1031 × 106
Ag-1051 × 1021 × 106
Ag-108m1 × 1011 × 106
Ag-110m1 × 1011 × 106
Ag-1111 × 1031 × 106
Cd-1091 × 1041 × 106
Cd-1151 × 1021 × 106
Cd-115m1 × 1031 × 106
In-1111 × 1021 × 106
In-113m1 × 1021 × 106
In-114m1 × 1021 × 106
In-115m1 × 1021 × 106
Sn-1131 × 1031 × 107
Sn-1251 × 1021 × 105
Sb-1221 × 1021 × 104
Sb-1241 × 1011 × 106
Sb-1251 × 1021 × 106
Te-123m1 × 1021 × 107
Te-125m1 × 1031 × 107
Te-1271 × 1031 × 106
Te-127m1 × 1031 × 107
Te-1291 × 1021 × 106
Te-129m1 × 1031 × 106
Te-1311 × 1021 × 105
Te-131m1 × 1011 × 106
Te-1321 × 1021 × 107
Te-1331 × 1011 × 105
Te-133m1 × 1011 × 105
Te-1341 × 1011 × 106
I-1231 × 1021 × 107
I-1251 × 1031 × 106
I-1261 × 1021 × 106
I-1291 × 1021 × 105
I-1301 × 1011 × 106
I-1311 × 1021 × 106
I-1321 × 1011 × 105
I-1331 × 1011 × 106
I-1341 × 1011 × 105
I-1351 × 1011 × 106
Xe-131+1 × 1041 × 104
Xe-1331 × 1031 × 104
Xe-1351 × 1031 × 1010
Cs-1291 × 1021 × 105
Cs-1311 × 1031 × 106
Cs-1321 × 1011 × 105
Cs-134+1 × 1031 × 105
Cs-1341 × 1011 × 104
Cs-1351 × 1041 × 107
Cs-1361 × 1011 × 105
Cs-137+1 × 1011 × 104
Cs-1381 × 1011 × 104
Ba-1311 × 1021 × 106
Ba-140+1 × 1011 × 105
La-1401 × 1011 × 105
Ce-1391 × 1021 × 106
Ce-1411 × 1021 × 107
Ce-1431 × 1021 × 106
Ce-144+1 × 1021 × 105
Pr-1421 × 1021 × 105
Pr-1431 × 1041 × 106
Nd-1471 × 1021 × 106
Nd-1491 × 1021 × 106
Pm-1471 × 1041 × 107
Pm-1491 × 1031 × 106
Sm-1511 × 1041 × 108
Sm-1531 × 1021 × 106
Eu-1521 × 1011 × 106
Eu-152m1 × 1021 × 106
Eu-1541 × 1011 × 106
Eu-1551 × 1021 × 107
Gd-1531 × 1021 × 107
Gd-1591 × 1031 × 106
Tb-1601 × 1011 × 106
Dy-1651 × 1031 × 106
Dy-1661 × 1031 × 106
Ho-1661 × 1031 × 105
Er-1691 × 1041 × 107
Er-1711 × 1021 × 106
Tm-1701 × 1031 × 106
Tm-1711 × 1041 × 108
Yb-1751 × 1031 × 107
Lu-1771 × 1031 × 107
Hf-1811 × 1011 × 106
Ta-1821 × 1011 × 104
W-1811 × 1031 × 107
W-1851 × 1041 × 107
W-1871 × 1021 × 106
Re-1861 × 1031 × 106
Re-1881 × 1021 × 105
Os-1851 × 1011 × 106
Os-1911 × 1021 × 107
Os-191m1 × 1031 × 107
Os-1931 × 1021 × 106
Ir-1901 × 1011 × 106
Ir-1921 × 1011 × 104
Pt-1911 × 1021 × 106
Pt-193m1 × 1031 × 107
Pt-1971 × 1031 × 106
Pt-197m1 × 1021 × 106
Au-1981 × 1021 × 106
Au-1991 × 1021 × 106
Hg-1971 × 1021 × 107
Hg-197m1 × 1021 × 106
Hg-2031 × 1021 × 105
Tl-2001 × 1011 × 106
Tl-2011 × 1021 × 106
Tl-2021 × 1021 × 106
Tl-2041 × 1041 × 104
Pb-2031 × 1021 × 106
Pb-210+1 × 1011 × 104
Pb-212+1 × 1011 × 105
Bi-2061 × 1011 × 105
Bi-2071 × 1011 × 106
Bi-2101 × 1031 × 106
Bi-212+1 × 1011 × 105
Po-2031 × 1011 × 106
Po-2051 × 1011 × 106
Po-2071 × 1011 × 106
Po-2101 × 1011 × 104
At-2111 × 1031 × 107
Rn-220+1 × 1041 × 107
Rn-222+1 × 1011 × 108
Ra-223+1 × 1021 × 105
Ra-224+1 × 1011 × 101
Ra-2251 × 1021 × 105
Ra-226+1 × 1011 × 104
Ra-2271 × 1021 × 106
Ra-228+1 × 1011 × 105
Ac-2281 × 1011 × 106
Th-226+1 × 1031 × 107
Th-2271 × 1011 × 104
Th-228+1 × 1001 × 104
Th-229+1 × 1001 × 103
Th-2301 × 1001 × 101
Th-2311 × 1031 × 107
Th-234+1 × 1031 × 105
Pa-2301 × 1011 × 106
Pa-2311 × 1001 × 103
Pa-2331 × 1021 × 107
U-2301 × 1011 × 105
U-2311 × 1021 × 107
U-232+1 × 1001 × 103
U-2331 × 1011 × 104
U-2341 × 1011 × 104
U-235+1 × 1011 × 104
U-2361 × 1011 × 104
U-2371 × 1021 × 106
U-238+1 × 1011 × 104
U-2391 × 1021 × 106
U-2401 × 1031 × 107
U-240+1 × 1011 × 106
Np-237+1 × 1001 × 103
Np-2391 × 1021 × 107
Np-2401 × 1011 × 106
Pu-2341 × 1021 × 107
Pu-2351 × 1021 × 107
Pu-2361 × 1011 × 104
Pu-2371 × 1031 × 107
Pu-2381 × 1001 × 104
Pu-2391 × 1001 × 104
Pu-2401 × 1001 × 103
Pu-2411 × 1021 × 105
Pu-2421 × 1001 × 104
Pu-2431 × 1031 × 107
Pu-2441 × 1001 × 104
Am-2411 × 1001 × 104
Am-2421 × 1031 × 106
Am-242m+1 × 1001 × 104
Am-243+1 × 1001 × 103
Cm-2421 × 1021 × 105
Cm-2431 × 1001 × 104
Cm-2441 × 1011 × 104
Cm-2451 × 1001 × 103
Cm-2461 × 1001 × 103
Cm-2471 × 1001 × 104
Cm-2481 × 1001 × 103
Bk-2491 × 1031 × 106
Cf-2461 × 1031 × 106
Cf-2481 × 1011 × 104
Cf-2491 × 1001 × 103
Cf-2501 × 1011 × 104
Cf-2511 × 1001 × 103
Cf-2521 × 1011 × 104
Cf-2531 × 1021 × 105
Cf-2541 × 1001 × 103
Es-2531 × 1021 × 105
Es-2541 × 1011 × 104
Es-254m1 × 1021 × 106
Fm-2541 × 1041 × 107
Fm-2551 × 1031 × 106
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”(2).1, or the concentration given in respect of that radionuclide in the document referenced in column 2.
(a)

not of natural terrestrial cosmic origin; or

(b)

listed in Table 1 of schedule 8.

The summation rule in respect of column 2 of Table 2 is the sum of the quotients A/B where—

(a)“A” means the concentration of each radionuclide listed in column 1 of Table 2 that is present in the radioactive material or radioactive waste; and

(b)“B” means the concentration of that radionuclide specified in column 2 of Table 2.

The summation rule in respect of column 3 of Table 2 is the sum of the quotients C/D where—

(a)“C” means the quantity of each radionuclide listed in column 1 of Table 2 that is present in the radioactive material or radioactive waste; and

(b)“D” means the quantity of that radionuclide specified in column 3 of Table 2.

+Parent radionuclides, and their progeny whose dose contributions are taken into account in the dose calculation (thus requiring only the exemption level of the parent radionuclide to be considered), are listed in the following:

Parent radionuclideProgeny
Sr-90Y-90
Zr-93Nb-93m
Zr-97Nb-97
Ru-106Rh-106
Ag-108mAg-108
Cs-137Ba-137m
Ba-140La-140
Ce-144Pr-144
Pb-210Bi-210, Po-210
Pb-212Bi-212, Tl-208 (0.36), Po-212 (0.64)
Bi-212Tl-208 (0.36), Po-212 (0.64)
Rn-220Po-216
Rn-222Po-218, Pb-214, Bi-214, Po-214
Ra-223Rn-219, Po-215, Pb-211, Bi-211, Tl-207
Ra-224Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Ra-226Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210
Ra-228Ac-228
Th-226Ra-222, Rn-218, Po-214
Th-228Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Th-229Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209
Th-234Pa-234 m
U-230Th-226, Ra-222, Rn-218, Po-214
U-232Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
U-235Th-231
U-238Th-234, Pa-234m
U-240Np-240 m
Np237Pa-233
Am-242mAm-242
Am-243Np-239
(1)

INTERNATIONAL ATOMIC ENERGY AGENCY, Categorization of Radioactive Sources, IAEA Safety Standards Series No. RS-G-1.9, IAEA, Vienna (2005).

(2)

1968 c.47 as relevantly amended by the Water Industry (Scotland) Act 2002 (asp 3), schedule 5, paragraph 41(b)(iv) and the Water Environment and Water Services (Scotland) Act 2003 (asp 3), schedule 3, paragraph 23(a).

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