Operational radiological safety

This chapter shall describe, for normal operational conditions  

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A.323. This section should provide the results of calculations of atmospheric diffusion parameters at the site boundary and at off-site locations, or refer to radionuclide atmospheric concentrations and dose calculations presented in Chapter A. 12 (Operational Radiological Safety) and Chapter A. 16 (Safety Analysis). 

A. 1241. This section shall give a conclusion regarding the acceptability of the operational radiological safety prognunmes and the design features at the facility. 

The licensing process consists of two steps construction and operating license that must be completed before fuel loading. Licensing covers radiological safety, environmental protection, and antitru,st considerations. Activities not defined as production or utilization of special nuclear material (SNM), use simple one-step. Materials Licenses, for the possession of radioactive materials. Examples are uranium mills, solution recovery plants, UO fabrication plants, interim spent fuel storage, and isotopic separation plants. 

The sanitary and epidemiological service of the Dnepropetrovsk district also provides supervision for the observance of radiological safety rates during operation of ionizing radiation sources in public health, industry and other industrial branches. It carries out studies on food products, drinking water, construction material, gamma-survey of the territory. 

Process Operation—Considerations from Radiological Safety Point of View.846... 

In view of the radiological safety the personal contact with operating installation should be minimized. The location of data acquisition and control systems has to be planned in separate room, away from places of potential contamination. However, the necessity of eventual periodic sampling has to be taken into account, too. The sampling points have to be located in the places with easy operator access and arranged in a way eliminating leaks and contamination. 

Swanson, W. P. Radiological Safety Aspects of the Operation of Electron Linear Accelerators IAEA Technical Report 188 International Atomic Energy Agency Vienna, Austria, 1979. 

The high operating temperature of the radioisotope thermionic converter poses difficult radiological safety... 

The PCS concept is based on experience from the development and operation of similar systems, giving high priority to nuclear and radiological safety. It ensures high reliability and system survivability even with equipment failures and operator errors and always provides adequate information to the operators. The system oisures presentation of information in a form convenient for the operators, optimizing the "man-machine" interface. 

Siting, design, construction, operation and sealing of near surfiice disposal facilities need to be carried out in such a way as to ensure that all radiological exposures are kept well within regulatory limits. The regulatory authorities prescribe the conditions, limitations and restrictions on the types, quantities, levels of activity, etc. of the wastes that may be disposed of in these facilities. It is essential to ensure compliance with such conditions, limitations and restrictions. In addition to radiological safety requirements, industrial safety requirements are also very important. 

The design shall exclude the permanent installation of piping or other equipment which could inadvertently (e.g. by acting as a siphon) lower the pool water elevation below the minimum operating level specified in the interests of radiological safety and protection of the fuel. 

INTERNATIONAL ATOMIC ENERGY AGENCY, Radiological Safety Aspects of the Operation of Neutron Generators, Safety Series No. 42, IAEA, Vienna (1976). 

The sum total of risks of the nuclear fuel cycle, most of which are associated with conventional industrial safety, are greater than those associated with nuclear power plant operation (30,35—39). However, only 1% of the radiological risk is associated with the nuclear fuel cycle so that nuclear power plant operations are the dominant risk (40). Pubhc perception, however, is that the disposition of nuclear waste poses the dominant risk. 

The Safety Goal Policy Statement was published to define acceptable radiological risk IVom nuclear power plant operation, and by implication provide a de minimus risk to be assured without cost considerations. Safety beyond the minimum requires cost-benefit analysis. Since being promulgated, bulletins and generic letters have been imposed to enhance safety, under the provisions of 10 CFR 50.109, the Backfit Rule. 

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