GB 11217-1989 The regulations for monitoring effluents at nuclear facilities
1 Subject content and application scope
This standard specifies the objectives for monitoring effluents at nuclear facilities, the principles and requirements for developing monitoring plans, technical requirements for sampling and measurement, as well as requirements for recording, reporting, and archiving measurement results.
This standard applies to monitoring effluents at all nuclear facilities involved in the processing and fabrication of radioactive material.
2 Terms
2.1 effluent
radioactive effluent in the Regulations, which is airborne and liquid radioactive waste discharged into the external environment via preset pathways from a nuclear facility, after passing through the waste treatment system and/or control equipment (including those for in-situ storage and decay)
2.2 nuclear facility
buildings and their internal equipment for the production, use, processing, and storage of highly and moderately radioactive material, including uranium or thorium smelting plants, nuclear reactors, radioisotope separation plants, nuclear fuel reprocessing plants, uranium (or thorium) fabrication plants, nuclear fuel element fabrication plants, Class A radiochemical laboratories, high-intensity irradiation sources, high-power particle accelerators, and radioactive waste treatment and storage facilities
2.3 effluent monitoring
sampling, analysis, or other measurements performed on effluents to characterize the radioactive material discharged from a nuclear facility into the external environment
2.4 unplanned release
release other than planned ones, including accidental releases
2.5 planned discharge
discharge indicated in the process flow diagram of a nuclear facility or scheduled by the competent authority, with the involved approximate activity (or specific activity), composition, and discharge time are known in advance
2.6 sampling
process of obtaining a quantity of sample proportional to time from the effluent over a specified period, using a representative sampling method
2.7 in-situ measurement
physical determination or chemical analysis of the effluent or its samples conducted on-site, providing rapid results
2.8 laboratory measurement
measurement or analysis of the collected samples which have been transported to a laboratory and subjected to specific physical or chemical treatments
2.9 plant discharge point
point where all discharge pipelines for effluents from a nuclear facility converge to form a main pipe, which connects to the environment
2.10 competent authority
government department or agency appointed or recognized by the State Council for specific objectives related to radiation protection and nuclear safety
2.11 authorized limit
quantitative limit for any radioactive component in effluents stipulated in the relevant standards issued by the national regulatory body
2.12 operational limit
quantitative limit for any radioactive component in effluents established by an operating organization itself to ensure compliance with the authorized limit
2.13 accuracy
parameter measured by trueness, representing the combination of systematic and random errors in a measurement result, indicating the degree of agreement between the measurement result and the true value
2.14 gross activity measurement
measurement of the activity of the effluent without distinguishing between nuclides within it, including the gross α, gross β, or gross γ activity
2.15 specific radionuclide determination
determination of the activity of any specific nuclide in the effluent or its sample using radiochemical separation, spectral analysis, or other methods
3 Effluent monitoring objectives and plan
3.1 Effluent monitoring objectives
3.1.1 To determine the quantity of radioactive material in the effluent from the facility for comparison with authorized limits or operational limits.
3.1.2 To provide source item data and information for applying appropriate environmental models to assess environmental quality and estimate radiation doses to the public.
3.1.3 To provide data and information for assessing whether the facility's operation and the performance of its radioactive waste treatment and control equipment are normal and effective.
3.1.4 To assure the public that radioactive releases from the nuclear facility are indeed under strict control.
3.1.5 To promptly detect and identify the nature (type) and scale of any unplanned release.
3.1.6 To provide information on whether activation of the alert system or emergency alarm system is required.
3.2 Effluent monitoring plan
Contents
1 Subject content and application scope
2 Terms
3 Effluent monitoring objectives and plan
4 Sampling and measuring techniques
5 Recording, reporting, and archiving of monitoring results
Annex A Report forms for results of monitoring effluents at nuclear facilities (Supplementary)
GB 11217-1989 The regulations for monitoring effluents at nuclear facilities
1 Subject content and application scope
This standard specifies the objectives for monitoring effluents at nuclear facilities, the principles and requirements for developing monitoring plans, technical requirements for sampling and measurement, as well as requirements for recording, reporting, and archiving measurement results.
This standard applies to monitoring effluents at all nuclear facilities involved in the processing and fabrication of radioactive material.
2 Terms
2.1 effluent
radioactive effluent in the Regulations, which is airborne and liquid radioactive waste discharged into the external environment via preset pathways from a nuclear facility, after passing through the waste treatment system and/or control equipment (including those for in-situ storage and decay)
2.2 nuclear facility
buildings and their internal equipment for the production, use, processing, and storage of highly and moderately radioactive material, including uranium or thorium smelting plants, nuclear reactors, radioisotope separation plants, nuclear fuel reprocessing plants, uranium (or thorium) fabrication plants, nuclear fuel element fabrication plants, Class A radiochemical laboratories, high-intensity irradiation sources, high-power particle accelerators, and radioactive waste treatment and storage facilities
2.3 effluent monitoring
sampling, analysis, or other measurements performed on effluents to characterize the radioactive material discharged from a nuclear facility into the external environment
2.4 unplanned release
release other than planned ones, including accidental releases
2.5 planned discharge
discharge indicated in the process flow diagram of a nuclear facility or scheduled by the competent authority, with the involved approximate activity (or specific activity), composition, and discharge time are known in advance
2.6 sampling
process of obtaining a quantity of sample proportional to time from the effluent over a specified period, using a representative sampling method
2.7 in-situ measurement
physical determination or chemical analysis of the effluent or its samples conducted on-site, providing rapid results
2.8 laboratory measurement
measurement or analysis of the collected samples which have been transported to a laboratory and subjected to specific physical or chemical treatments
2.9 plant discharge point
point where all discharge pipelines for effluents from a nuclear facility converge to form a main pipe, which connects to the environment
2.10 competent authority
government department or agency appointed or recognized by the State Council for specific objectives related to radiation protection and nuclear safety
2.11 authorized limit
quantitative limit for any radioactive component in effluents stipulated in the relevant standards issued by the national regulatory body
2.12 operational limit
quantitative limit for any radioactive component in effluents established by an operating organization itself to ensure compliance with the authorized limit
2.13 accuracy
parameter measured by trueness, representing the combination of systematic and random errors in a measurement result, indicating the degree of agreement between the measurement result and the true value
2.14 gross activity measurement
measurement of the activity of the effluent without distinguishing between nuclides within it, including the gross α, gross β, or gross γ activity
2.15 specific radionuclide determination
determination of the activity of any specific nuclide in the effluent or its sample using radiochemical separation, spectral analysis, or other methods
3 Effluent monitoring objectives and plan
3.1 Effluent monitoring objectives
3.1.1 To determine the quantity of radioactive material in the effluent from the facility for comparison with authorized limits or operational limits.
3.1.2 To provide source item data and information for applying appropriate environmental models to assess environmental quality and estimate radiation doses to the public.
3.1.3 To provide data and information for assessing whether the facility's operation and the performance of its radioactive waste treatment and control equipment are normal and effective.
3.1.4 To assure the public that radioactive releases from the nuclear facility are indeed under strict control.
3.1.5 To promptly detect and identify the nature (type) and scale of any unplanned release.
3.1.6 To provide information on whether activation of the alert system or emergency alarm system is required.
3.2 Effluent monitoring plan
Contents of GB 11217-1989
Contents
1 Subject content and application scope
2 Terms
3 Effluent monitoring objectives and plan
4 Sampling and measuring techniques
5 Recording, reporting, and archiving of monitoring results
Annex A Report forms for results of monitoring effluents at nuclear facilities (Supplementary)
