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GB 11929-2011: Regulations for designing storage building of high level radioactive liquid waste
Status: Valid GB 11929: Evolution and historical versions
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| GB 11929-2011 | English | 259 |
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Regulations for designing storage building of high level radioactive liquid waste
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GB 11929-2011
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| GB 11929-1989 | English | 359 |
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Regulations for designing storage building of high level radioactive liquid waste
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Basic data | Standard ID | GB 11929-2011 (GB11929-2011) | | Description (Translated English) | Regulations for designing storage building of high level radioactive liquid waste | | Sector / Industry | National Standard | | Classification of Chinese Standard | F49 | | Classification of International Standard | 27.120 | | Word Count Estimation | 11,113 | | Date of Issue | 2011-12-30 | | Date of Implementation | 2012-12-01 | | Older Standard (superseded by this standard) | GB 11929-1989 | | Quoted Standard | GB 18871; EJ 588; EJ/T 681; EJ 849; EJ 877; EJ/T 938; EJ/T 939 | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 23 of 2011 | | Issuing agency(ies) | General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China | | Summary | This Chinese standard applies to high level radioactive waste (hereinafter referred to as"high-level radioactive waste") involved in designing storage building technical requirements. This standard applies to spent fuel reprocessing high-level radioactive waste generated by the storage facility design | GB 11929-2011: Regulations for designing storage building of high level radioactive liquid waste
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Regulations for designing storage building of high level radioactive liquid waste
ICS 27.120
F49
National Standards of People's Republic of China
Replacing GB 11929-1989
High level radioactive liquid waste storage plant design regulations
Issued on. 2011-12-30
2012-12-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Table of Contents
Preface Ⅰ
1 Scope 1
2 Normative references 1
3 1 General Provisions
4 Storage Plant 1
Sump 4 5
6 Radioactive Waste Management 5
7 safety analysis and environmental impact assessment 5
8 radiation safety and monitoring measures 6
Emergency 9 consider 6
10 6 retired to consider
Foreword
All technical contents of this standard are mandatory.
This standard was drafted in accordance with GB/T 1.1-2009 given rules.
This standard replaces GB 11929-1989 "high-level radioactive liquid waste storage plant design requirements." This standard and GB 11929-1989
Compared to, in addition to editorial changes, the major technical changes are as follows.
--- Normative documents used instead of GB 18871 and GB 4792 GB 8703; increased EJ588, EJ849, EJ877,
EJ/T 681, EJ/T 938, EJ/T 939;
--- Remove the "Terminology" section;
--- Remove the "Site Selection" section;
--- In the General emphasized the "high level liquid waste storage plant is part of the reprocessing plant, reprocessing plant site should be in the same building."
(See 3.1);
--- Increased plant building (structure) building materials, systems and components grading requirements (see 4.1);
--- Original standard Appendix A canceled, moved to table of contents 4.3.1 of this standard, and revised accordingly;
--- Increasing the building ventilation system design requirements (see 4.3.4);
--- Content of the original standard 10.1,10.2,10.3 moved to this standard 4.3 "storage plant design principles", as the 4.3.5,
4.3.6,4.3.7, and has been amended accordingly;
--- Increasing the water storage tank and fill acid plant (see 5.1.9);
--- Increased acidity tank testing requirements (see 5.2c));
--- Increased Chapter 6, "Radioactive Waste Management," adds radioactive waste minimization considerations, and the original standard 9.1.4,
9.1.5 The contents moved to this chapter (see Chapter 6);
--- Chapter 7, "Safety analysis and environmental impact assessment" has been modified in accordance with the relevant provisions of EJ/T 681, the original standard 8.1
"Maximum credible accident" and 8.2 "accident prevention" as a merger of this standard 7.1 "Security Analysis", the content was streamlined
And improve and increase the requirements for the preparation of the safety analysis report (see 7.1.3);
--- Chapter 8 has been modified in accordance with the relevant provisions of GB 18871 and EJ849;
--- Chapter 9, "to consider emergency" in "emergency measures" based on the original standard on Chapter 10 has been modified, the original standard of 10.1 to 10.3
Moved to this standard 4.3, this chapter is mainly considering the design stage of its consideration of the emergency;
--- According EJ588 adds "retired to consider" (see Chapter 10);
--- Remove Appendix A.
The standard proposed by China National Nuclear Corporation.
This standard by the National Standardization Technical Committee on Nuclear Energy (SAC/TC58) centralized.
This standard was drafted. China Nuclear Power Engineering Co., Ltd.
The main drafters of this standard. Li Si Fan, Lu Tao, Chen Yong, Liu Ying, Lu spring.
This standard replaces the previous standard published case.
--- GB 11929-1989.
High level radioactive liquid waste storage plant design regulations
1 Scope
The standard provides a high level radioactive waste (hereinafter referred to as "high-level liquid waste") storage plant design technical requirements involved.
This standard applies to produce spent fuel reprocessing high level liquid waste storage plant design.
2 Normative references
The following documents for the application of this document is essential. For dated references, only the dated version suitable for use herein
Member. For undated references, the latest edition (including any amendments) applies to this document.
GB 18871 ionizing radiation protection and safety of radiation sources basic standards
EJ588 nuclear fuel reprocessing plant decommissioning radiation protection
Standard format and content of EJ/T 681 nuclear fuel reprocessing plant safety analysis report
EJ849 nuclear fuel reprocessing plant radiation safety design requirements
EJ877 nuclear fuel reprocessing plant safety design guidelines
After EJ/T 938 nuclear fuel reprocessing plant, ventilation and air purification design requirements
EJ/T 939 nuclear fuel processing plant was built after grading criteria (structure) building materials, systems and components
3 General
3.1 high level liquid waste storage plant is part of the reprocessing plant, reprocessing plant should be at the same site construction, and built close to high level liquid waste
Making facilities, to avoid long-distance transport.
3.2 Design should ensure safe, reliable and practical, to minimize the generation of radioactive waste and radioactive substances secondary to environmental release
Heavy volume.
3.3 design work should be carried out safety analysis and environmental impact assessment.
3.4 Plant design should ensure radiation safety, and follow the ALARA principle.
3.5 in tank design should be a comprehensive analysis of various factors affecting the critical safety and, if necessary, take all reasonably practicable measures to ensure
Criticality safety certificate.
3.6 plant design should meet the requirements of the seismic and other external events defense.
3.7 should be designed to meet the requirements for emergency and decommissioning.
3.8 Design should develop quality assurance program.
3.9 Design of the tank should be clearly defined design lifetime.
3.10 high level liquid waste storage plant design should follow GB 18871, EJ588, EJ849, EJ877 and other design-related provisions.
4 storage plant
4.1 storage building building (structure) grade buildings, systems and components
To ensure the implementation of the nuclear safety functions, deal with high-level radioactive waste storage plant building (structure) building materials, systems and components division level of safety, and roots
According to the security level to determine the seismic classification, grading and quality assurance design, manufacturing, procurement requirements. Classification principles see EJ/T 939.
4.2 Storage Plant composition
4.2.1 Process Plant storage system components
High level liquid waste storage plant process systems should include the following components.
a) high-level radioactive waste storage tanks and waste transportation equipment;
b) high-level liquid waste tank mixing system;
c) high-level radioactive waste liquid cooling system;
d) high-level radioactive waste storage tank dilution air and process exhaust aftertreatment system;
e) other auxiliary systems.
4.2.2 Storage Plant Building
4.2.2.1 concrete shielding equipment room
High level liquid waste storage tanks and ancillary equipment with radioactive process used should be provided in sufficient thickness of the shield of reinforced concrete provided
Preparation room.
4.2.2.2 Process trench and valve chamber
Pipeline transportation of radioactive waste, the valve should be arranged in the pipe trench technology with shield and valve chamber.
4.2.2.3 cladding and liquid collection pit
Radiological equipment room, valve chamber and process pipe trench should be lined by plane, and should be selected corrosion, irradiation, facing materials easy decontamination, the surface of the bottom cover
Department should make certain slope and let drip hole at the lowest point.
4.2.2.4 Install the access area
For installation, maintenance radiological equipment, installation and maintenance area should be set up.
4.2.2.5 Process control room and other ancillary buildings
Including professional (water, heating, electricity, gas, etc.) buildings, gates and other health.
4.3 storage plant design principles
4.3.1 high level liquid waste storage plant shall be arranged in accordance with GB 18871 standards, the radiation in the workplace is divided into control and supervised areas, in order to
In radiation protection management and control of occupational exposure, and in accordance with the EJ849, according to the level and extent of possible radiation contamination, and then control
Area is divided into three sub-areas, namely green zone, orange zone and the red zone, white zone is supervised areas. The district should have a reasonable airflow and vacuum requirements, specific points
District principles in Table 1.
4.3.2 high level liquid waste storage plant design should follow the principle of defense in depth. Wherein the multiple barriers including tanks and piping systems, equipment room
Stainless steel cladding, concrete equipment room, building ventilation systems. Equipment room should be provided to withstand the weight of the entire structure, permeability and small
Geotechnical radionuclides have higher adsorption capacity, to ensure the safety of the tank.
4.3.3 high level liquid waste storage building should be designed in accordance with the single failure criterion to ensure the reliability of the system, which assumes a system in any one
Case of a single component failure can still correctly performing a predetermined system functions.
Table 1 plant partition principle
Regional Reference feature engaged in radiation work crowd control plant
Supervised area
(Usually no special
Means of protection or security
Regional measures, but need
Often occupational exposures Article
Member monitoring and evaluation)
White areas
(Non-radioactive work area)
Is not in contact with radioactive plant
Radioactive work area, generally
Clean
Staff generally do not enter this area
Clothes need to be replaced
Control area
(Needs and may require
Special protective measures or safety
Region-wide measures)
Green Zone
(Operation radioactive work area)
Class person staying in this area also
Is safe, there appear soiled surface
Pollution and aerosol pollution may
, But timely detection and elimination
The area between the entrance through the establishment of health
Orange Area
(Radioactive equipment maintenance area)
District personnel are not often stay
Field maintenance personnel subject to the anti-radiation
Care professionals allowed to enter
jobs
Entering this zone should be subject to health personnel
Air gates and gate
Red Zone
(Radioactive device area)
Direct storage of radioactive materials
Area, external radiation is usually
Strong, serious pollution
Usually people are not allowed to enter only after
Too full decontamination, at a dose of personnel closely monitored
Under Governor, to enter this area maintenance
Ventilation System 4.3.4 Design of the plant shall be subject to the provisions of EJ/T 938's.
4.3.5 sump should set up an independent emergency cooling system in normal cooling water supply is interrupted, the waste to ensure that the temperature inside the tank is still below
60 ℃.
4.3.6 should be set up within the plant emergency air pressure, ensure the normal air pressure inside the tank supply disruption hydrogen concentration in the air is still below the safety limit control
4.1% (volume percent).
4.3.7 should be set up within the plant emergency power to ensure external power supply is interrupted, the process cooling systems, instrumentation and control systems mainly normal operation
Access channel and the control room and lighting needs.
4.4 tank equipment room
4.4.1 The equipment room design requirements
4.4.1.1 equipment room should be buried below ground.
4.4.1.2 equipment room should be lined with stainless steel cladding, should take the form of full-cladding. In order to ensure the construction quality of the cladding, the design should be regulated
Given the quality of welding and weld cladding surface inspection requirements.
Bottom cladding 4.4.1.3 equipment room should be made of a certain slope and let drip hole at the lowest point.
4.4.1.4 liquid collecting pit equipment room should be set at a waste transfer leakage and decontamination equipment waste equipment.
4.4.1.5 Design measures should be taken to prevent surface water or groundwater into the equipment room, cutting off all possible sources of the channel to prevent the tank being immersed
Bubble and float.
Inspection hole should be provided with sufficient equipment and emergency entrances case of an accident on the equipment room roof 4.4.1.6.
4.4.2 The equipment room testing requirements
4.4.2.1 liquid collecting pit equipment room should be set up signal level meter, signal meter should meet the requirements of multiple or diversity, in order to detect the sump
leakage.
4.4.2.2 Equipment should be located aerosol detection apparatus.
4.5 storage plant maintenance
4.5.1 For large high-level waste storage tank (volume more than 100m3), time to consider the design overhaul, once the waste leakage should occur in a timely manner
Down to spare slot.
4.5.2 In addition to large, high-level liquid waste tank, other process equipment, piping valves, meters and other measures should be overhauled or replaced have.
5 tank
5.1 sump design requirements
5.1.1 sump tank components and materials should be corrosion-resistant metal material according to the characteristics of its interior materials.
5.1.2 The tank should be set aside. Spare tank sump same design requirements, and should use the maximum volume of the same groove.
5.1.3 The tank should meet the structural strength and seismic requirements, with sufficient corrosion allowance.
5.1.4 should be located within the sump cooling device, and meet one hundred percent reserve.
5.1.5 should be diluted and discharged radiolysis hydrogen tank within the tank to maintain negative pressure state, the air tank volume of hydrogen concentrations below
4.1%.
5.1.6 shall be provided within the tank stirring device, stirring manner and intensity should be avoided solid bottom sediment compaction.
5.1.7 shall be provided with reliable sampling device, sampling should be at different depths, to ensure getting a representative sample.
5.1.8 Sample storage tank should be set within a certain number of coupons, in order to meet the requirements of multiple sampling, including the base metal and weld samples, as in-service inspection
One of the measures.
5.1.9 sump unit should be set up water and acid.
5.1.10 tank floor and sidewalls welds shall be 100% of the X-ray fluoroscopy.
5.1.11 shall ensure that the lower inner tank pressure abnormality protection sump.
5.1.12 should be located within the tank cleaning apparatus for storage tank decommissioning.
5.1.13 quality assurance program should be developed on the tank material, manufacturing, installation, commissioning and testing of the quality put forward specific requirements.
5.2 sump internal testing requirements
Inner tank requires selection of radiation-resistant, corrosion-resistant, high reliability of an instrument, and should meet regularly inspect, repair, replacement requirements. Correct
Some important process parameters such as temperature, level, concentration of hydrogen or diversity should be set multiple measuring instruments.
Sump test items include.
a) continuous level measurement;
b) through the full signal and alarm;
c) waste density and acidity;
d) waste temperature and high-temperature alarm;
e) cooling water inlet temperature;
f) tank vapor pressure;
g) tank vapor phase hydrogen concentration continuous monitoring and alarming;
h) cooling water for continuous monitoring of radioactive contamination.
5.3 high level liquid waste transport
5.3.1 high-level radioactive waste should be disposed in the delivery tube of stainless steel cladding laid pipe trench.
5.3.2 storage tank within the high-level radioactive waste should be discharged multiplicity or diversity of the delivery device. Try to ensure that the waste is emptied.
5.3.3 between the plant and outside of the plant as well as the inside of the plant, between the transmission of high-level liquid waste and receive high level liquid waste shall complete the job settings
Good communication means of communication, to ensure the safe and reliable operation, accurate.
5.3.4 The design should try to prevent the accumulation of waste in the pipeline, to avoid clogging the pipe, and the necessary measures to remove the blockage should be set.
6 Radioactive Waste Management
6.1 Radioactive Waste Management general requirements
Storage building should be designed to minimize the generation of secondary radioactive waste and radioactive substances released to the environment should be lower than the specified
Limits and kept as low as reasonably achievable.
6.2 radioactive liquid waste
Secondary radioactive liquid waste generated during the normal operation and maintenance of storage inside the plant, the concentration should be sent to the appropriate level and composition, respectively
Waste treatment plant or storage.
6.3 radioactive aerosol
Radioactive aerosol into the atmosphere should be taken before purification and filtration, and other effective measures through chimneys gaseous effluent discharge
Radioactive emission concentration is less than a predetermined concentration.
6.4 solid radioactive waste
Solid radioactive waste generated during operation of the repair process should be separately collected for further processing.
7 safety analysis and environmental impact assessment
7.1 Safety Analysis
7.1.1 Design of response may lead to abnormal release of radioactive material anticipated operational occurrences, design basis accidents and serious safety
analysis.
7.1.2 for a variety of events and incidents as defined in 7.1.1, should take the necessary precautions in the design, including detailed instructions to run people
Countermeasures members should be taken to prevent the release of radioactive material exceeds the acceptable limit.
7.1.3 should be prepared safety analysis report, the format and content of the safety analysis report should be implemented in accordance with the relevant provisions of EJ/T 681's.
7.2 Environmental Impact Assessment
7.2.1 shall analyze and evaluate the impact of normal operation on the environment.
7.2.2 shall analyze and evaluate the impact of the incident on the environment conditions.
7.2.3 propose environmental protection measures should be taken.
8 radiation safety and monitoring measures
8.1 Radiation Safety
8.1.1 Control Principle dose
8.1.1.1 Radiation protection should be designed to comply with the relevant provisions of GB 18871 and the EJ849.
8.1.1.2 taking into account the economic and social factors in the future, individual radiation dose, and the possibility that the number of photos are kept reasonably achievable
As far as possible low. Control principles and calculation of effective dose should implement the relevant provisions of GB 18871.
8.1.2 radiation shielding design
8.1.2.1 Storage plant radiation shield shall be designed to ensure that the Radiation Workers annual effective doses lower than approved by the regulatory authorities of the
Dose constraint value.
8.1.2.2 design should determine the maximum variation range of the storage building of the received high-level radioactive waste radioactivity should be calculated when the shield
Leeway.
8.1.2.3 shield can not leave through-holes and crevices, where a duct, pipes, cables, etc. through the shield, steps should be taken to ensure that no
Significantly weaken the shielding effect of the shield. It can be used in the form of penetrations.
8.1.2.4 In response to the binding site shielding material cut through radiation shielding necessary compensation.
8.2 Radiation Monitoring
8.2.1 shall be provided a fixed γ monitor installed in a place where staff may stay or γ-ray dose rate may be abnormal changes
Home, for remote monitoring, exceeds a predetermined limit, the automatic alarm signal. Not set fixed monitoring point locations should be used portable (can
Portable) dose meter monitoring.
8.2.2 shall be provided a fixed aerosol air sampling system in the plant, sampled periodically monitored. Not set a fixed place of sampling points, using mobile
Aerosol sampler sampling monitoring.
8.2.3 should be set radioactive aerosol monitor, tank equipment for indoor air monitoring to analyze and judge the storage tank leaks.
8.2.4 Staff should be set monitoring tools inside and outside the irradiation dose.
8.2.5 response when the plant floor, walls, equipment, regular monitoring of surface contamination exceeds the limits specified in the national standard, should be promptly
Decontamination.
8.2.6 cooling water storage tank should be monitored by radioactivity after passing the order to be discharged into the environment.
8.2.7 In the area around the storage tank should be based on the flow of groundwater and hydrogeological situation, reasonably well disposed to detect, so regular monitoring of well water
The concentration of radioactive nuclides and components.
Emergency 9 consider
Take emergency measures in case of accidents should be considered when designing the required conditions, such as venues, roads, vehicles, facilities, equipment, communications liaison
condition.
10 retired to consider
10.1 at the design stage should meet the requirements of the future decommissioning of the plant.
10.2 radiological equipment, piping and equipment room cladding, etc. should be easy decontamination, equipment room stainless steel cladding require smooth and clean, reduce cladding ride
Connected components, reducing flushing less than the dead, unobstructed fluid can be discharged in order to provide convenient conditions for decommissioning. Stainless steel cladding is not installed and
We need chemical decontamination of concrete floors or walls should be covered with easy decontamination materials to minimize contamination of the concrete. It should be easy to install
Necessary temporary decontamination wash pipe.
Site and plant layout space 10.3 should provide the necessary decommissioning, plant arrangement should be easy to build a gas account, temporary shielding and mobile ventilation means
Makes it possible that equipment, pipes, valves demolition, hanging out and transport, as well as to prevent persons, objects cross-contamination.
10.4 structural design should consider the additional load when decommissioning or after retirement.
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