LegalizeThe Natural Mineral Water, Spring Water and Bottled Drinking Water (Scotland) (No. 2) Regulations 2007
- (1) If a food authority determines that spring water or bottled drinking water does not comply with the parametric concentrations or values set out in this Schedule, the food authority must—
- (a) immediately investigate the non-compliance in order to identify the cause;
- (b) assess whether the non-compliance poses a risk to human health which requires action;
- (c) require the business operator to take remedial action as soon as possible to restore the quality of the water and, where necessary, protect human health;
- (d) in respect of any parameter specified in the tables in Parts 2 and 3, notify the general public of the remedial action taken, unless the food authority considers that non-compliance with the parametric value is trivial; and
- (e) in respect of any parameter specified in the table in Part 2, notify the general public of the risks and remedial action taken and advise the general public of any additional precautionary measures that may be needed for the protection of human health in respect of radioactive substances.
- (2) If spring water or bottled drinking water constitutes a potential danger to human health, irrespective of whether it meets the relevant parametric values in this Schedule, a food authority must—
- (a) prohibit or restrict the supply of that water in its area or take such other action as is necessary to protect human health; and
- (b) inform the general public promptly of that fact and provide advice where necessary.
- (3) In performing the functions in paragraph (2), the food authority must have regard to any risks to human health which would be caused by an interruption of the supply or a restriction in the use of water intended for human consumption.
PART 2 — Minimum sampling and analysis frequencies
| (1)The volumes are calculated as averages taken over a calendar year. | (1)The volumes are calculated as averages taken over a calendar year. |
|---|---|
| (2)As far as possible, the number of samples should be distributed equally in time and location. | (2)As far as possible, the number of samples should be distributed equally in time and location. |
| Volume of water bottled each daym ³[^f01000] | Number of samples per year[^f01001] |
| volume ≤ 100 | 1 |
| 100 < volume ≤ 1,000 | 1 |
| 1,000 < volume ≤ 10,000 | 1+1 for each 3,300 m³/d and part thereof of the total volume |
| 10, 000 < volume ≤ 100,000 | 3+1 for each 10,000 m³/d and part thereof of the total volume |
| volume > 100,000 | 10+1 for each 25,000 m³/d and part thereof of the total volume |
PART 3 — Parametric values for radon, tritium and indicative dose
| (1)Remedial action is deemed to be justified on radiological protection grounds, without further consideration, where radon concentrations exceed 1000 Bq/l. | (1)Remedial action is deemed to be justified on radiological protection grounds, without further consideration, where radon concentrations exceed 1000 Bq/l. | (1)Remedial action is deemed to be justified on radiological protection grounds, without further consideration, where radon concentrations exceed 1000 Bq/l. | (1)Remedial action is deemed to be justified on radiological protection grounds, without further consideration, where radon concentrations exceed 1000 Bq/l. |
|---|---|---|---|
| (2)Elevated levels of tritium may indicate the presence of other artificial radionuclides. If the tritium concentration exceeds its parametric value, an analysis of the presence of other artificial radionuclides shall be required. | (2)Elevated levels of tritium may indicate the presence of other artificial radionuclides. If the tritium concentration exceeds its parametric value, an analysis of the presence of other artificial radionuclides shall be required. | (2)Elevated levels of tritium may indicate the presence of other artificial radionuclides. If the tritium concentration exceeds its parametric value, an analysis of the presence of other artificial radionuclides shall be required. | (2)Elevated levels of tritium may indicate the presence of other artificial radionuclides. If the tritium concentration exceeds its parametric value, an analysis of the presence of other artificial radionuclides shall be required. |
| Item | Parameter | Unit of Measurement | Parametric Value |
| 1. | Radon | Bq/l | 100 [^f01002] |
| 2. | Tritium | Bq/l | 100 [^f01003] |
| 3. | indicative dose | mSv | 0.10 |
SCHEDULE 13 — Sampling and analysis for indicative dose in spring water and bottled drinking water
PART 1 — General
Analysis of samples
1
Each food authority must ensure that each sample is analysed and indicative dose calculated in accordance with Annex III to Directive 2013/51 and this Schedule.
2
For each radionuclide specified in the second column of Table 1 in Part 2, the derived concentration is shown in the third column of that table and the dose coefficient for calculating the indicative dose is specified in Table A of Annex III to Directive 96/29 as referenced in Annex III to Directive 2013/51.
3
For each parameter specified in the first column of Table 2 in Part 2, the method of analysis must be one that is capable of detecting the parameter at the limit of detection specified in the second column of that table.
PART 2
| (1)This table includes values for the most common natural and artificial radionuclides; these are precise values, calculated for a dose of 0.1 mSv, an annual intake of 730 litres and using the dose coefficients laid down in Table A of Annex III to Directive 96/29; derived concentrations for other radionuclides can be calculated on the same basis, and values can be updated on the basis of more recent information recognised by the competent authorities in the Member State. | (1)This table includes values for the most common natural and artificial radionuclides; these are precise values, calculated for a dose of 0.1 mSv, an annual intake of 730 litres and using the dose coefficients laid down in Table A of Annex III to Directive 96/29; derived concentrations for other radionuclides can be calculated on the same basis, and values can be updated on the basis of more recent information recognised by the competent authorities in the Member State. | (1)This table includes values for the most common natural and artificial radionuclides; these are precise values, calculated for a dose of 0.1 mSv, an annual intake of 730 litres and using the dose coefficients laid down in Table A of Annex III to Directive 96/29; derived concentrations for other radionuclides can be calculated on the same basis, and values can be updated on the basis of more recent information recognised by the competent authorities in the Member State. |
|---|---|---|
| (2)This table allows only for the radiological properties of uranium, not for its chemical toxicity. | (2)This table allows only for the radiological properties of uranium, not for its chemical toxicity. | (2)This table allows only for the radiological properties of uranium, not for its chemical toxicity. |
| Methods of analysis and performance characteristics[^f01004] | Methods of analysis and performance characteristics[^f01004] | Methods of analysis and performance characteristics[^f01004] |
| Table 1 | Table 1 | Table 1 |
| Derived concentrations for radioactivity in spring water or bottled drinking water | Derived concentrations for radioactivity in spring water or bottled drinking water | Derived concentrations for radioactivity in spring water or bottled drinking water |
| Origin | Nuclide | Derived concentration |
| Natural | U-238[^f01005] | 3.0 Bq/l |
| U-234[^f01005] | 2.8 Bq/l | |
| Ra-226 | 0.5 Bq/l | |
| Ra-228 | 0.2 Bq/l | |
| Pb-210 | 0.2 Bq/l | |
| Po-210 | 0.1 Bq/l | |
| Artificial | C-14 | 240 Bq/l |
| Sr-90 | 4.9 Bq/l | |
| Pu-239/Pu-240 | 0.6 Bq/l | |
| Am-241 | 0.7 Bq/l | |
| Co-60 | 40 Bq/l | |
| Cs-134 | 7.2 Bq/l | |
| Cs-137 | 11 Bq/l | |
| I-131 | 6.2 Bq/l | |
| (1)The limit of detection is calculated according to the ISO standard 11929: Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionising radiation – Fundamentals and application, with probabilities of errors of 1st and 2nd kind of 0.05 each. | (1)The limit of detection is calculated according to the ISO standard 11929: Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionising radiation – Fundamentals and application, with probabilities of errors of 1st and 2nd kind of 0.05 each. | (1)The limit of detection is calculated according to the ISO standard 11929: Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionising radiation – Fundamentals and application, with probabilities of errors of 1st and 2nd kind of 0.05 each. |
| --- | --- | --- |
| (2)Measurement uncertainties are calculated and reported as complete standard uncertainties, or as expanded standard uncertainties with an expansion factor of 1.96, according to the ISO Guide for the Expression of Uncertainty in Measurement. | (2)Measurement uncertainties are calculated and reported as complete standard uncertainties, or as expanded standard uncertainties with an expansion factor of 1.96, according to the ISO Guide for the Expression of Uncertainty in Measurement. | (2)Measurement uncertainties are calculated and reported as complete standard uncertainties, or as expanded standard uncertainties with an expansion factor of 1.96, according to the ISO Guide for the Expression of Uncertainty in Measurement. |
| (3)The limit of detection for tritium and for radon is 10% of its parametric value of 100 Bq/l. | (3)The limit of detection for tritium and for radon is 10% of its parametric value of 100 Bq/l. | (3)The limit of detection for tritium and for radon is 10% of its parametric value of 100 Bq/l. |
| (4)The limit of detection for gross alpha activity and gross beta activities are 40% of the screening values of 0.1 and 1.0 Bq/l respectively. | (4)The limit of detection for gross alpha activity and gross beta activities are 40% of the screening values of 0.1 and 1.0 Bq/l respectively. | (4)The limit of detection for gross alpha activity and gross beta activities are 40% of the screening values of 0.1 and 1.0 Bq/l respectively. |
| (5)This limit of detection applies only to initial screening for ID for a new water source. If initial checking indicates that it is not plausible that Ra-228 exceeds 20% of the derived concentration, the limit of detection may be increased to 0.08 Bq/l for routine Ra-228 nuclide specific measurements, until a subsequent re-check is required. | (5)This limit of detection applies only to initial screening for ID for a new water source. If initial checking indicates that it is not plausible that Ra-228 exceeds 20% of the derived concentration, the limit of detection may be increased to 0.08 Bq/l for routine Ra-228 nuclide specific measurements, until a subsequent re-check is required. | (5)This limit of detection applies only to initial screening for ID for a new water source. If initial checking indicates that it is not plausible that Ra-228 exceeds 20% of the derived concentration, the limit of detection may be increased to 0.08 Bq/l for routine Ra-228 nuclide specific measurements, until a subsequent re-check is required. |
| Parameters radionuclides | Limit of detection[^f01006][^f01007] | |
| Tritium | 10 Bq/l[^f01008] | |
| Radon | 10 Bq/l[^f01008] | |
| gross alpha activitygross beta activity | 0.04 Bq/l[^f01009]0.4 Bq/l[^f01009] | |
| U-238 | 0.02 Bq/l | |
| U-234 | 0.02 Bq/l | |
| Ra-226 | 0.04 Bq/l | |
| Ra-228 | 0.02 Bq/l[^f01010] | |
| Pb-210 | 0.02 Bq/l | |
| Po-210 | 0.01 Bq/l | |
| C-14 | 20 Bq/l | |
| Sr-90 | 0.4 Bq/l | |
| Pu-239/Pu-240 | 0.04 Bq/l | |
| Am-241 | 0.06 Bq/l | |
| Co-60 | 0.5 Bq/l | |
| Cs-134 | 0.5 Bq/l | |
| Cs-137 | 0.5 Bq/l | |
| I-131 | 0.5 Bq/l |
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