This standard specifies the monitoring purposes of nuclear facility effluents, principles and requirements for preparing monitoring plans, sampling and measurement technical requirements, and recording, reporting and archiving requirements for measurement results. This standard applies to effluent monitoring from all nuclear facilities that handle and process radioactive materials. GB 11217-1989 General provisions for monitoring effluent from nuclear facilities GB11217-1989 Standard download and decompression password: www.bzxz.net

National Standards of the People's Republic of China
General regulations for monitoring effluents-at nuclear facilities
1 Subject content and scope of application
GB11217- -89
This standard specifies the monitoring purposes of nuclear facility effluents, principles and requirements for preparing monitoring plans, sampling and measurement technical requirements, and recording, reporting and archiving requirements for measurement results. This standard applies to effluent monitoring from all nuclear facilities involving the handling and processing of radioactive materials. 2° Terminology
2.1 Effluent
In these regulations, it is the abbreviation of radioactive effluent. It refers to airborne and liquid radioactive waste that is discharged from a nuclear facility to the external environment through a predetermined route after passing through the waste treatment system and/or control equipment (including on-site storage and decay). 2.2 Nuclear facilities
Buildings and internal equipment that produce, use, process and store strong and relatively strong radioactive materials. Including uranium and needle smelters, nuclear reactors, radioisotope separation plants, nuclear fuel reprocessing plants, uranium (or eluium) processing plants, nuclear fuel element plants, Class A radiochemical laboratories, strong radiation sources, high-power particle accelerators, radioactive waste processing and storage facilities, etc. 2.3 Effluent monitoring
Sampling, analyzing or other measurements of effluents to describe the characteristics of radioactive flows discharged from nuclear facilities to the external environment. 2.4 Unplanned release
All releases other than planned releases, including accidental releases. 2.5 Planned emissions
For emissions that have been marked in the process flow diagram of the nuclear facility, or are planned and arranged by the competent authority, their approximate activity (or specific activity), composition, and emission time are all known in advance of. 2.6 Sampling
is to use representative sampling methods to obtain a certain amount of samples from the effluent within a certain period of time that is proportional to time. 2.7 On-site measurement
is performed on the effluent or its sample on site Physical determination or chemical analysis, results can be obtained quickly. 2.8 Laboratory measurement
Transport the collected samples back to the laboratory, and then measure or analyze them after certain physical or chemical treatments. 2.9 General discharge outlet
In a nuclear facility, all discharge pipes of effluents are brought together to form a main pipe. The point where the main pipe meets the environment is called the main discharge outlet. 2.10 Competent Authority
A government department or agency appointed or recognized by the State Council for specific purposes related to radiation protection and nuclear safety. 2.11 Management Limits
National Environmental Protection Administration 1989-03-16 Approved for implementation on 1990-01-01
GB1121789
Among the effluents specified in the relevant standards issued by the national supervision department Quantity limits for radioactive components. 2.12 Operating limits
In order to ensure that the requirements of management limits are met. Quantity limits for radioactive components in effluents set by the operating unit itself. 2.13 Accuracy
is measured by accuracy. It is the combination of systematic error and random error in the measurement results, indicating the degree of consistency between the measurement results and the true value. 2.14 Total activity measurement
does not distinguish between measurements of nuclear cords in the effluent, including measurements of total alpha, total or total activity. 2.15 Specific radionuclide measurement
Use radiochemical separation method or energy spectrum analysis method or other methods to measure the radioactive activity of several nuclides in the effluent or its sample.
3 Purpose and plan of effluent monitoring
3.1 Purpose of effluent monitoring
3.1.1 Determine the amount of radioactive material in the effluent of this facility so that it can be consistent with management limits or operating limits for comparison. 3.1.2 Provide source data and information for applying appropriate environmental models to evaluate environmental quality and estimate doses to the public. 3.1.3 Provide data and information to determine whether the operation of the facility and the radioactive waste treatment and control devices are working normally and effectively. 3.1.4 Convince the public that radioactive releases from nuclear facilities are indeed strictly controlled. 3.1.5 Quickly discover and identify the nature (type) and scale of unplanned releases. 3.1.6 Give information on whether the alarm system or emergency alarm system needs to be activated. 3.2 Plan for effluent monitoring
3.2.1 Principles of preparation
Any unit with effluent monitoring tasks should prepare an effluent monitoring plan according to the principle of optimization and submit it to the superior authority and supervision Department filing. Explanatory materials should be attached when necessary. 3.2.2 General requirements
3.2.2.1 The monitoring plan shall meet the monthly requirements set forth in Article 3.1 of this regulation. 3.2.2.2 When formulating the monitoring plan, special attention should be paid to the characteristics of various nuclear facilities and the possibility of unplanned releases. 3.2.2.3 In the monitoring plan, all effluents that are expected or may have radioactive contamination should be placed under routine monitoring. 3.2.2.4 The location of the monitoring point must be reasonably selected so that the monitoring results at this point can represent the actual emissions. Monitoring points should be located within the nuclear facility, downstream of the waste treatment system or control device, taking into account accessibility and feasibility. 3.2.2.5 The sampling and measurement frequency and the types of nuclides to be monitored should be reasonably determined. The types of nuclides to be monitored shall not be less than the number of nuclides that may be emitted by this facility with management limits. 3.2.2.6 Within a nuclear facility, if any emission point is confirmed to meet one of the following conditions based on the design indicators of the facility and after a period of monitoring, and with the consent of the competent department and the supervisory department, it may be exempted from the discharge point. For monitoring: a. Compared with the implemented standards, only a small amount or a very low concentration of radioactive material is released. b. A small share of the total effluent from the facility. 3.2.2.7 In order to reasonably evaluate the monitoring results, in addition to radioactivity monitoring, other relevant physical and chemical parameters should be measured as needed (such as chemical composition of effluents, particle size distribution, exhaust flow, sewage flow, smoke windows and sampling The temperature and humidity in the pipeline. For large nuclear facilities, the wind direction, wind speed and other relevant meteorological data at the discharge outlet must also be measured). 3.2.2.8 Instruments used for routine monitoring should have a wide enough range to accommodate monitoring of unplanned releases. For monitoring instruments used at critical release points, residual technology must be considered.
3.2.2.9 The operating unit of a nuclear facility should conduct analysis and determination of specific nuclides according to the needs of the facility or the requirements of the competent department and supervisory department. | |tt | The types and proportions of nutrients are clear and basically fixed. b. The radioactivity or specific activity of the effluent is really low (less than one percent or less of the regulatory limit), so that it is impossible or unnecessary to carry out the measurement of specific nuclide, but the radioactivity level must be confirmed When very low. 3.2.2.11 Monitoring system flow charts for airborne effluents and liquid effluents should be drawn separately. The sampling points and measurement points should be marked on the diagram, and different symbols should be used to distinguish the sampling and measurement methods. When the system is relatively complex, a table should be used to explain the measurement tasks and measurement methods undertaken by the sampling points and monitoring points. The purpose, method, location, sampling frequency and measurements to be taken of the sampling points should be explained. For the measurement point, the measurement tasks and measurement technical requirements should be explained, especially the measurement method, measurement-related shielding, calibration, detection limit and measurement reliability, etc. 3.2.3 Airborne effluent monitoring plan
3.2.3.1 A monitoring plan should be developed based on analysis of the flow diagram of the ventilation system or exhaust system. The relevant information such as flow rate, pressure difference, temperature, humidity and flow rate should be marked in the above flow chart, so that appropriate monitoring points can be selected accordingly. 3.2.3.2 The optimal sampling and measurement frequency and required additional information are determined by the discharge mode of the effluent, the discharge rate, and the characteristics of the discharged radioactive materials and their changes over time. 3.2.3.3 When there is a high possibility of unplanned release, the monitoring plan should require the installation of alarm devices, and should also include measurement of relevant air parameters, such as wind speed and direction, temperature gradient, etc. 3.2.3.4 Monitoring plans for airborne effluents from various nuclear facilities should pay attention to the following special issues: a. Typical monitoring systems for nuclear power plants and other power reactors should include continuous measurement of inert gases, continuous sampling of 13I and radioactive aerosols, and their experiments Room measurements are taken regularly.
b. In addition to routine monitoring of the mixture of radionuclides and specific nuclides specified in its operating license, a nuclear power plant should also conduct a detailed analysis of all radionuclide components every quarter. c.For nuclear fuel reprocessing plants, under normal operating conditions, only 5Kt and 1311 in the smoke need to be continuously measured. For samples obtained by continuous sampling, \H, 14C, 12UI, 13I, steel series elements and other particles that emit beta or rays should also be measured regularly in the laboratory. d. For uranium processing plants and ring processing plants, the main purpose is to monitor alpha radionuclides in the effluent, and the focus of monitoring should be on the continuous sampling system of aerosols.
e. For research reactors, under normal operating conditions, the requirements for monitoring systems are the same as those for general power reactors. However, due to the specific type of reactor and the types of experiments performed, the range of possible accident releases is wide, and special considerations must be given to sampling and measurement equipment accordingly.
f. For radiochemistry laboratories, monitoring plans vary depending on the radionuclides handled in the laboratory. For large hot chambers that handle irradiated nuclear fuel, it is necessary to monitor the inert gases in the effluent; for some specialized laboratories, it is necessary to monitor 14C and fluorinated water vapor in the effluent. For airborne effluents from such laboratories, , continuous sampling is required to monitor radioactive halogen elements and radioactive aerosols. For laboratories producing radioisotopes and hot cells for metallurgical inspection, continuous sampling and periodic measurements of the smoke windows are required, or continuous measurements are required. g For particle accelerators that may produce radioactive aerosols, regular aerosol sampling and measurement should be carried out; if fluorine targets are used, the sampling and measurement of atmosphere should be increased.
3.2.4 Monitoring plan for liquid effluent
3.2.4.1 A monitoring plan should be developed based on the analysis of the process flow chart of the liquid effluent, and monitoring points or sampling points should be set up reasonably. Relevant information should be marked on the flow chart, including the volume of the wastewater tank or wastewater pool, the physical and chemical characteristics of the waste liquid to be discharged, the designed generation rate and discharge rate, etc.
3.2.4.2 Intermediate storage equipment that collects waste liquids with different radioactivity levels and chemical characteristics respectively shall implement predetermined monitoring procedures before discharge, including sampling and measuring radioactive activity that meet the requirements. The type and content of measurements that need to be performed depend on the regulations on emission limits (operating limits or management limits) and the type and activity of the nuclide to be emitted. 3.2.4.3 If the conditions of 3.2.2.10 are met, the discharge can be implemented after measuring only the total activity. In addition, only in emergencies or other special circumstances, it is allowed to discharge after measuring the total activity, but the sample must be retained, and then the analysis and determination of specific nuclides can be completed for reporting purposes.
3.2.4.4 When a nuclear facility has a large amount of radioactive waste liquid that is to be continuously discharged into the receiving water body, a blue test GB11217-89
point should be set up on each: - discharge pipe; if any For the main discharge outlet, a final monitoring point must also be established at the main discharge outlet. Samples proportional to the emission volume are collected continuously or regularly at each of the above monitoring points, and their radioactive components are regularly analyzed in the laboratory. When the specific activity of radioactive waste liquid is very low (less than one-tenth of the operating limit), regular sampling can be used instead of continuous sampling. 3.2.4.5 When the possibility of unplanned release of liquid waste from a nuclear facility is high, or when it contains key nuclides, a continuous monitoring device should be installed in the discharge pipeline or at the main discharge outlet. The device should have alarms and automatic termination of release. function. 3.2.4.6 Plans for monitoring liquid effluents from various nuclear facilities should pay attention to the following special issues: a. Nuclear power plants and other power reactors must continuously or periodically analyze and measure H, 5Co, \Sr, Sr, Ru, The concentration and total amount of nuclides specified in the operating license for 134Cs, 137Cs, etc., and a full analysis of all radionuclide components should be done every quarter. b. Nuclear fuel reprocessing plants must continuously or regularly analyze and measure the concentration and total amount of 137Cs, Sr, 103Ru-106Ru, 95Zr-95Nb, 238U, 239Pu and other nuclides in the liquid effluent. A complete analysis of all radionuclides should be done quarterly. c. For uranium and ring processing plants and uranium and needle refineries, the main purpose is to monitor alpha radionuclides in the effluent and other nuclides that should be monitored based on the materials being operated, such as 2\Pb, etc. d. For research reactors, due to different specific types of reactors and types of experiments conducted, the nuclides to be monitored should be different, and the monitoring plan should fully reflect these characteristics. e. For radiochemistry laboratories, the types of radionuclides in liquid effluent vary with the experimental content, and the monitoring plan should fully reflect this feature.
1. The types of nuclides contained in the liquid effluents from various particle accelerators and radioisotope separation plants also vary depending on the facility. When formulating a monitoring plan, the priorities should be clearly defined and the key points should be highlighted. 4 Sampling and measurement technology
4.1 Sampling method
4.1.1 When the concentration of radionuclides in the effluent and/or its emission rate vary widely (the variation range of the emission flow rate is within ±50 % ~ ± 100% or even greater), or when the possibility of unplanned release is high or when unplanned release is expected to cause serious environmental or social harm, continuous and proportional sampling should be used. 4.1.2 When the concentrations of all radionuclides in the effluent are relatively constant and no abnormal changes occur, regular sampling can be used. 4.1.3 For both continuous discharge and intermittent discharge, the decision whether to adopt continuous sampling or periodic sampling shall be made according to the provisions of 4.1.1 and 4.1.2.
4.1.4 When an abnormal situation occurs during the operation of a nuclear facility and an unplanned release occurs, special sampling should be arranged in a timely manner. 4.2 Sampling technology
4.2.1 Sampling technology should meet the following requirements;: 4.2.1.1 Timeliness: A sufficient amount of samples must be obtained within the required time or time interval. 4.2.1.2 Representativeness: It should be ensured that the composition of the sample contains all radionuclides in the effluent, except for concentration or dilution to meet the requirements of the measurement technique (in this case, the concentration or dilution factor is Predictable or calculable), without causing additional dilution or concentration effects
4:2.2 In principle, any sampling technology that can meet the requirements of 4.2.1 can be used, but standard sampling should be used as much as possible technology. When there is no standard sampling technology for the time being or when non-standard sampling technology needs to be used for other reasons, approval or consent must be obtained in advance from the competent authority and supervisory authority.
4.2.3 For airborne effluents, the sampling technology that should be used shall be in accordance with relevant regulations. 4.2.4 For liquid effluents, when discharging intermittently, the waste liquid in the wastewater tank should be fully stirred before sampling. During continuous discharge, if the flow rate changes greatly, proportional sampling should be used; if the flow rate is fairly constant, regular sampling can be performed. 4.2.5 For routine monitoring, in order to reduce the amount of detailed measurements required to assess the consequences of releasing radioactive waste, some or all of the individual representative samples may be mixed into composite samples 4.2.6 Within the scope of any monitoring site When selecting sampling points, accessibility and feasibility should be considered while ensuring sampling representativeness (overall representativeness or partial representativeness). 4.3 Measurement methods
GB11217-89
4.3.1 There are two methods of measurement for effluent monitoring: direct measurement and on-site measurement after sampling or laboratory measurement. These two methods can be used independently or, if necessary, at the same time to verify or supplement each other. Which measurement method is used is determined by the accuracy requirements of the data or the level of technical development of the measurement. 4.4 Measurement technology
4.4.1 Measurement technology should meet the requirements set forth by management limits or operational limits. 4.4.2 Standard measurement technology should be used as much as possible. When there is no standard measurement technology for the time being and non-standard measurement technology needs to be used, a written report must be reported to the competent department and supervisory department, and it can be used only after obtaining approval. 4.4.3. Under the same conditions as described in 4.1.1, when monitoring by direct measurement, continuous measurement should be used. For any device used for continuous measurement, its lowest detectable limit should be at or less than one percent of the operating limit, and the width of its measuring range should be able to meet the measurement requirements for unplanned releases. If necessary, a device with several trigger thresholds should be installed. Chain alarm device. 4.4.4 At key emission points, in order to reliably monitor accident releases in addition to conventional monitoring, two sets of independent monitoring devices must be installed. One set is used for routine monitoring and the other is used for incident monitoring. Devices used for accident monitoring require a large measurement range (for example, using less sensitive or shielded detectors) and be equipped with an alarm device. 4.4.5 Laboratory measurement is a reliable method for complete analysis of radionuclides in effluents. Interference factors should be reduced or eliminated as much as possible, and concentrated samples suitable for measurement should be prepared to achieve better results than direct measurement or on-site measurement. The sensitivity that can be achieved is higher. 4.5 Quality Assurance
The sampling and measurement of effluents should comply with the relevant provisions of GB11216 "General Requirements for Quality Assurance Plans for Monitoring Quality Assurance of Effluents from Nuclear Facilities and Radioactivity in the Environment".
5 Recording, reporting and archiving of monitoring results
5.1 Recording of monitoring results
5.1.1 The monitoring department for nuclear facility effluents shall develop a uniform format recording form in accordance with the requirements of these regulations. 5.1.2 The recorded original data should be subjected to appropriate data processing, including statistical analysis and unit conversion, so that it can meet the requirements of the report. 5.1.3 Monitoring results should record the following: name of nuclear facility, type and source of effluent, discharge point (or release point), measurement and sampling point, type of nuclide (or mixture) discharged, discharge time, discharge continuation Time, discharge flow rate, sampling time, sampling duration, sampling volume, total volume of effluent during the sampling period, measurement time, measurement result (including error). 5.1.4 For key discharge points, it is also necessary to record: the flow rate of the receiving water body (for liquid effluent), the discharge height (for airborne effluent), and meteorological data (including wind direction, wind speed, atmospheric stability, and precipitation). 5.1.5 When intermittent or batch discharge is implemented, the information required in 5.1.3 and 5.1.4 must be recorded for each batch. 5.1.6 For unplanned releases, in addition to recording the content required in 5.1.3 and 5.1.4 (the release time is calculated from the moment when the unplanned release is detected by monitoring, or from a certain time reasonably inferred from this), it is also necessary to The reasons for unplanned releases should be documented. 5.1.7 The person in charge of each monitoring project should sign on the monitoring results to show responsibility. 5.2 Report of monitoring results
5.2.1 A report on monitoring results shall be submitted to the competent department and supervisory department in accordance with the requirements of these regulations. 5.2.2 The content and format of the monitoring results report should meet the following requirements: 5.2.2.1 A summary statement with appropriate illustrations and explanatory information to indicate what different characteristics or events occurred during the period covered by this report and their as a result of. Use standard terminology and keep the content simple. 5.2.2.2 Monitoring system flow chart. If this diagram is a new diagram modified from the original diagram, additional modification instructions should be attached. 5.2.2.3 Effluent monitoring results data sheet. The format of the data table is suitable for computer storage. The form adopts the unified format in Appendix A of these regulations.
5.2.2.4 The report should also have the following additional instructions: GB11217—89
a. A brief description of the monitoring method used, the lowest detection limit of the method and the total error in the measurement results. b. When only measuring the total α, total β and total activity of the effluent, state the assumed composition of the nuclide mixture and the timeframe for reporting based on 5.2.3:
5.2.3.1 Routine monitoring report, For general nuclear facilities, this is submitted every six months. 5.2.3.2 For those nuclear facilities that discharge a large amount of radioactive materials or have a high activity (as approved by the competent department in conjunction with the supervisory department), routine monitoring reports shall be submitted once every quarter. 5.2.3.3 In the event of a serious unplanned release event, the release time, release volume and monitoring results should be reported in a timely manner. The reporting time shall not be later than 48 hours from the time when monitoring detects an unplanned release. If the incident constitutes an accident, national regulations on accident reporting shall be implemented. 5.3 Archiving and storage time of monitoring results
5.3.1 The original records of monitoring results should be archived in the monitoring department of the nuclear facility. 5.3.2 The original copy of the monitoring results report should be archived in the nuclear facility operating unit. 5.3.3 Monitoring results (including original records and original reports) must be kept for at least ten years after the facility is decommissioned. The types of documents to be permanently preserved shall be approved by the competent department in conjunction with the supervisory department. Name of nuclear facility:
1. Split and activated gas
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
2. Iodine
a. Total emissions of 131I
b. Average emission rate in this period
c. Accounting for management Percentage of limit value
3. Particles
a. Particles with half-life >8d
b, average emission rate during this period
c. Percentage of management limits
d, total alpha radioactivity
4. Atmosphere
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
GB11217-89
Appendix A
Nuclear facility effluent monitoring results report form
(Supplement)
Monitoring Department :
Table A1
Single
Time Range:
Airborne Effluent
Bit
Ba
Bg/ s
%
Bq
Ba/s
%
Bg
Bq/s
%||tt ||B
Ba
Bg/s
%
quarter
Responsible person:
Total emissions
degree
quarter
degree
Total error of estimate, %
Nuclide released
1. Split gas
BEKr|| tt||5mKr
kr
eKr
Isaxe
135mXe
ae xe
Iam Xe
Others (specified )
Unknown nature
Total of this period
2. Iodine
1331
1851
Total of this period|| tt||3. Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)|| tt||Unknown nature
Total of this period
Unit
B
Ba
Bq
Table A2||tt| |GB11217—89
Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree||tt| |Batch mode:
degree
released nuclides
1. Fragment gas
asKr
asmkr
BTKr||tt ||BaKr
xe
155mXe
135Xe
laan Xe
Others (specified)
Unknown nature||tt| |Total of this period
2. Iodine
311
11
1351
Total of this period
3.Particles|| tt||Bsr
pesr
.18ACs
131cs
1wBa-140La
Other (specified)
Unknown nature| |tt||Total for this period
1. Fission products and activation products
Unit
Bq
Bq
Bq
a .Total emissions (excluding fluorine, gas, α)b, average concentration after dilution during this period
c. Percentage of administrative limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
5. When intermittent or batch discharge is implemented, the information required in 5.1.3 and 5.1.4 must be recorded for each batch. 5.1.6 For unplanned releases, in addition to recording the content required in 5.1.3 and 5.1.4 (the release time is calculated from the moment when the unplanned release is detected by monitoring, or from a certain time reasonably inferred from this), it is also necessary to The reasons for unplanned releases should be documented. 5.1.7 The person in charge of each monitoring project should sign on the monitoring results to show responsibility. 5.2 Report of monitoring results
5.2.1 A report on monitoring results shall be submitted to the competent department and supervisory department in accordance with the requirements of these regulations. 5.2.2 The content and format of the monitoring results report should meet the following requirements: 5.2.2.1 A summary statement with appropriate illustrations and explanatory information to indicate what different characteristics or events occurred during the period covered by this report and their as a result of. Use standard terminology and keep the content simple. 5.2.2.2 Monitoring system flow chart. If this diagram is a new diagram modified from the original diagram, additional modification instructions should be attached. 5.2.2.3 Effluent monitoring results data sheet. The format of the data table is suitable for computer storage. The form adopts the unified format in Appendix A of these regulations.
5.2.2.4 The report should also have the following additional instructions: GB11217—89
a. A brief description of the monitoring method used, the lowest detection limit of the method and the total error in the measurement results. b. When only measuring the total α, total β and total activity of the effluent, state the assumed composition of the nuclide mixture and the timeframe for reporting based on 5.2.3:
5.2.3.1 Routine monitoring report, For general nuclear facilities, this is submitted every six months. 5.2.3.2 For those nuclear facilities that discharge a large amount of radioactive materials or have a high activity (as approved by the competent department in conjunction with the supervisory department), routine monitoring reports shall be submitted once every quarter. 5.2.3.3 In the event of a serious unplanned release event, the release time, release volume and monitoring results should be reported in a timely manner. The reporting time shall not be later than 48 hours from the time when monitoring detects an unplanned release. If the incident constitutes an accident, national regulations on accident reporting shall be implemented. 5.3 Archiving and storage time of monitoring results
5.3.1 The original records of monitoring results should be archived in the monitoring department of the nuclear facility. 5.3.2 The original copy of the monitoring results report should be archived in the nuclear facility operating unit. 5.3.3 Monitoring results (including original records and original reports) must be kept for at least ten years after the facility is decommissioned. The types of documents to be permanently preserved shall be approved by the competent department in conjunction with the supervisory department. Name of nuclear facility:
1. Split and activated gas
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
2. Iodine
a.Total emission of 131I
b. Average emission rate of this period
c.Accounting for management Percentage of limit value
3. Particles
a. Particles with half-life >8d
b, average emission rate during this period
c. Percentage of management limits
d, total alpha radioactivity
4. Atmosphere
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
GB11217-89
Appendix A
Nuclear facility effluent monitoring results report form
(Supplement)
Monitoring department :
Table A1
Single
Time Range:
Airborne Effluent
Bit
Ba
Bg/ s
%
Bq
Ba/s
%
Bg
Bq/s
%||tt ||B
Ba
Bg/s
%
quarter
Responsible person:
Total emissions
Degree
Quarter
Degree
Total error of estimate, %
Nuclide released
1. Fragment gas
BEKr|| tt||5mKr
kr
eKr
Isaxe
135mXe
ae xe
Iam Xe
Others (specified )
Unknown nature
Total of this period
2. Iodine
1331
1851
Total of this period|| tt||3. Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)|| tt||Unknown nature
Total of this period
Unit
B
Ba
Bq
Table A2||tt| |GB11217—89
Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree||tt| |Batch mode:
degree
released nuclides
1. Fragment gas
asKr
asmkr
BTKr||tt ||BaKr
xe
155mXe
135Xe
laan Xe
Others (specified)
Unknown nature||tt| |Total of this period
2. Iodine
311
11
1351
Total of this period
3.Particles|| tt||Bsr
pesr
.18ACs
131cs
1wBa-140La
Other (specified)
Unknown nature| |tt||Total for this period
1. Fission products and activation products
Unit
Bq
Bq
Bq
a .Total emissions (excluding fluorine, gas, α)b, average concentration after dilution during this period
c. Percentage of regulatory limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
5. When intermittent or batch discharge is implemented, the information required in 5.1.3 and 5.1.4 must be recorded for each batch. 5.1.6 For unplanned releases, in addition to recording the content required in 5.1.3 and 5.1.4 (the release time is calculated from the moment when the unplanned release is detected by monitoring, or from a certain time reasonably inferred from this), it is also necessary to The reasons for unplanned releases should be documented. 5.1.7 The person in charge of each monitoring project should sign on the monitoring results to show responsibility. 5.2 Report of monitoring results
5.2.1 A report on monitoring results shall be submitted to the competent department and supervisory department in accordance with the requirements of these regulations. 5.2.2 The content and format of the monitoring results report should meet the following requirements: 5.2.2.1 A summary statement with appropriate illustrations and explanatory information to indicate what different characteristics or events occurred during the period covered by this report and their as a result of. Use standard terminology and keep the content simple. 5.2.2.2 Monitoring system flow chart. If this diagram is a new diagram modified from the original diagram, additional modification instructions should be attached. 5.2.2.3 Effluent monitoring results data sheet. The format of the data table is suitable for computer storage. The form adopts the unified format in Appendix A of these regulations.
5.2.2.4 The report should also have the following additional instructions: GB11217—89
a. A brief description of the monitoring method used, the lowest detection limit of the method and the total error in the measurement results. b. When only measuring the total α, total β and total activity of the effluent, state the assumed composition of the nuclide mixture and the timing of the report based on 5.2.3:
5.2.3.1 Routine monitoring report, For general nuclear facilities, this is submitted every six months. 5.2.3.2 For those nuclear facilities that discharge a large amount of radioactive materials or have a high activity (as approved by the competent department in conjunction with the supervisory department), routine monitoring reports shall be submitted once every quarter. 5.2.3.3 In the event of a serious unplanned release event, the release time, release volume and monitoring results should be reported in a timely manner. The reporting time shall not be later than 48 hours from the time when monitoring detects an unplanned release. If the incident constitutes an accident, national regulations on accident reporting shall be implemented. 5.3 Archiving and storage time of monitoring results
5.3.1 The original records of monitoring results should be archived in the monitoring department of the nuclear facility. 5.3.2 The original copy of the monitoring results report should be archived in the nuclear facility operating unit. 5.3.3 Monitoring results (including original records and original reports) must be kept for at least ten years after the facility is decommissioned. The types of documents to be permanently preserved shall be approved by the competent department in conjunction with the supervisory department. Name of nuclear facility:
1. Split and activated gas
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
2. Iodine
a. Total emissions of 131I
b. Average emission rate in this period
c. Accounting for management Percentage of limit value
3. Particles
a. Particles with half-life >8d
b, average emission rate during this period
c. Percentage of management limits
d, total alpha radioactivity
4. Atmosphere
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
GB11217-89
Appendix A
Nuclear facility effluent monitoring results report form
(Supplement)
Monitoring department :
Table A1
Single
Time Range:
Airborne Effluent
Bit
Ba
Bg/ s
%
Bq
Ba/s
%
Bg
Bq/s
%||tt ||B
Ba
Bg/s
%
quarter
Responsible person:
Total emissions
Degree
Quarter
Degree
Total error of estimate, %
Nuclide released
1. Fragment gas
BEKr|| tt||5mKr
kr
eKr
Isaxe
135mXe
ae xe
Iam Xe
Others (specified )
Unknown nature
Total of this period
2. Iodine
1331
1851
Total of this period|| tt||3. Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)|| tt||Unknown nature
Total of this period
Unit
B
Ba
Bq
Table A2||tt| |GB11217—89
Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree||tt| |Batch mode:
degree
released nuclides
1. Fragment gas
asKr
asmkr
BTKr||tt ||BaKr
xe
155mXe
135Xe
laan Xe
Others (specified)
Unknown nature||tt| |Total of this period
2. Iodine
311
11
1351
Total of this period
3.Particles|| tt||Bsr
pesr
.18ACs
131cs
1wBa-140La
Other (specified)
Unknown nature| |tt||Total for this period
1. Fission products and activation products
Unit
Bq
Bq
Bq
a .Total emissions (excluding fluorine, gas, α)b, average concentration after dilution during this period
c. Percentage of administrative limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
2. For those nuclear facilities that discharge a large amount of radioactive materials or have a high activity (as determined by the competent department in conjunction with the supervisory department), routine monitoring reports shall be submitted quarterly. 5.2.3.3 In the event of a serious unplanned release event, the release time, release volume and monitoring results should be reported in a timely manner. The reporting time shall not be later than 48 hours from the time when monitoring detects an unplanned release. If the incident constitutes an accident, national regulations on accident reporting shall be implemented. 5.3 Archiving and storage time of monitoring results
5.3.1 The original records of monitoring results should be archived in the monitoring department of the nuclear facility. 5.3.2 The original copy of the monitoring results report should be archived in the nuclear facility operating unit. 5.3.3 Monitoring results (including original records and original reports) must be kept for at least ten years after the facility is decommissioned. The types of documents to be permanently preserved shall be approved by the competent department in conjunction with the supervisory department. Name of nuclear facility:
1. Split and activated gas
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
2. Iodine
a. Total emissions of 131I
b. Average emission rate in this period
c. Accounting for management Percentage of limit value
3. Particles
a. Particles with half-life >8d
b, average emission rate during this period
c. Percentage of management limits
d, total alpha radioactivity
4. Atmosphere
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
GB11217-89
Appendix A
Nuclear facility effluent monitoring results report form
(Supplement)
Monitoring department :
Table A1
Single
Time Range:
Airborne Effluent
Bit
Ba
Bg/ s
%
Bq
Ba/s
%
Bg
Bq/s
%||tt ||B
Ba
Bg/s
%
quarter
Responsible person: www.bzxz.net
Total emissions
Degree
Quarter
Degree
Total error of estimate, %
Nuclide released
1. Fragment gas
BEKr|| tt||5mKr
kr
eKr
Isaxe
135mXe
ae xe
Iam Xe
Others (specified )
Unknown nature
Total of this period
2. Iodine
1331
1851
Total of this period|| tt||3. Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)|| tt||Unknown nature
Total of this period
Unit
B
Ba
Bq
Table A2||tt| |GB11217—89
Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree||tt| |Batch mode:
degree
released nuclides
1. Fragment gas
asKr
asmkr
BTKr||tt ||BaKr
xe
155mXe
135Xe
laan Xe
Others (specified)
Unknown nature||tt| |Total of this period
2. Iodine
311
11
1351
Total of this period
3.Particles|| tt||Bsr
pesr
.18ACs
131cs
1wBa-140La
Other (specified)
Unknown nature| |tt||Total for this period
1. Fission products and activation products
Unit
Bq
Bq
Bq
a .Total emissions (excluding fluorine, gas, α)b, average concentration after dilution during this period
c. Percentage of regulatory limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
2. For those nuclear facilities that discharge a large amount of radioactive materials or have a high activity (as determined by the competent department in conjunction with the supervisory department), routine monitoring reports shall be submitted quarterly. 5.2.3.3 In the event of a serious unplanned release event, the release time, release volume and monitoring results should be reported in a timely manner. The reporting time shall not be later than 48 hours from the time when monitoring detects an unplanned release. If the incident constitutes an accident, national regulations on accident reporting shall be implemented. 5.3 Archiving and storage time of monitoring results
5.3.1 The original records of monitoring results should be archived in the monitoring department of the nuclear facility. 5.3.2 The original copy of the monitoring results report should be archived in the nuclear facility operating unit. 5.3.3 Monitoring results (including original records and original reports) must be kept for at least ten years after the facility is decommissioned. The types of documents to be permanently preserved shall be approved by the competent department in conjunction with the supervisory department. Name of nuclear facility:
1. Split and activated gas
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
2. Iodine
a. Total emissions of 131I
b. Average emission rate in this period
c. Accounting for management Percentage of limit value
3. Particles
a. Particles with half-life >8d
b, average emission rate during this period
c. Percentage of management limits
d, total alpha radioactivity
4. Atmosphere
a, total emissions
b. The average emission rate during this period
c. Percentage of management limits
GB11217-89
Appendix A
Nuclear facility effluent monitoring results report form
(Supplement)
Monitoring department :
Table A1
Single
Time Range:
Airborne Effluent
Bit
Ba
Bg/ s
%
Bq
Ba/s
%
Bg
Bq/s
%||tt ||B
Ba
Bg/s
%
quarter
Responsible person:
Total emissions
Degree
Quarter
Degree
Total error of estimate, %
Nuclide released
1. Fragment gas
BEKr|| tt||5mKr
kr
eKr
Isaxe
135mXe
ae xe
Iam Xe
Others (specified )
Unknown nature
Total of this period
2. Iodine
1331
1851
Total of this period|| tt||3. Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)|| tt||Unknown nature
Total of this period
Unit
B
Ba
Bq
Table A2||tt| |GB11217—89
Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree||tt| |Batch mode:
degree
released nuclides
1. Fragment gas
asKr
asmkr
BTKr||tt ||BaKr
xe
155mXe
135Xe
laan Xe
Others (specified)
Unknown nature||tt| |Total of this period
2. Iodine
311
11
1351
Total of this period
3.Particles|| tt||Bsr
pesr
.18ACs
131cs
1wBa-140La
Other (specified)
Unknown nature| |tt||Total for this period
1. Fission products and activation products
Unit
Bq
Bq
Bq
a .Total emissions (excluding fluorine, gas, α)b, average concentration after dilution during this period
c. Percentage of regulatory limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)
Unknown nature of
total for this period
unit
B
Ba
Bq
Table A2
GB11217—89| |tt||Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree
Batch mode:
Degree
Nuclide released
1. Split gas
asKr
asmkr
BTKr
BaKr|| tt||xe
155mXe
135Xe
laan Xe
Other (specified)
Unknown nature
Total of this period
2. Iodine
311
11
1351
Total for this period
3. Particles
Bsr| |tt||pesr
.18ACs
131cs
1wBa-140La
Others (specified)
Unknown nature
This Total time
1. Fission products and activation products
Unit
Bq
Bq
Bq
a. Total emissions ( Excluding fluorine and gas, α)b, average concentration after dilution during this period
c. Percentage of regulatory limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
Particles
sr
aosr
134Cs
Larcs
J40Ba-140La
Others (specified)
Unknown nature of
total for this period
unit
B
Ba
Bq
Table A2
GB11217—89| |tt||Airborne effluent
Quarterly
Overhead release
Quarterly
Continuous mode:
Degree
Batch mode:
Degree
Nuclide released
1. Split gas
asKr
asmkr
BTKr
BaKr|| tt||xe
155mXe
135Xe
laan Xe
Other (specified)
Unknown nature
Total of this period
2. Iodine
311
11
1351
Total for this period
3. Particles
Bsr| |tt||pesr
.18ACs
131cs
1wBa-140La
Others (specified)
Unknown nature
This Total time
1. Fission products and activation products
Unit
Bq
Bq
Bq
a. Total emissions ( Excluding fluorine and gas, α)b, average concentration after dilution during this period
c. Percentage of regulatory limits
GB11217—89
Table A3
Airborne effluents
Quarterly
Table A4 liquid effluents||tt| |Unit
Bq
B/L
%
Ground release
Quarterly
Total emissions
Quarterly| |tt||Continuous mode:
Quarterly
Quarterly
Batch mode:
Quarterly
Total estimated error, %
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