Radiation Protection Programme

The estimated radiation exposure of the staff and the general public in accident conditions shall be analysed in Chapter A. 16 (Safety Analysis). Exposure from anticipated operational occurrences shall be within the bounds laid down in the accident analysis and, therefore, shall also be described in Chapter A. 16. Radiological emergency planning is described in Chapter A.20 (Emergency Planning and Preparedness), and irradiated fuel management should be treated in Chapter A. 10 (Auxiliary Systems). 

The health physics facilities and equipment, such as laboratories for radioactive analysis, contamination control equipment and decontamination facilities, shall be described, including the location of these facilities, as well as the arrangements for maintenance and calibration of health physics instruments and for personnel monitoring (e.g. film badge and thermoluminescent dosimetry service). 

This section shall describe the radiation and contamination monitoring stations, including fixed hand and foot monitors, portal monitors (if used) and portable activity monitors located at these stations. The portable and laboratory equipment and instrumentation for performing radiation and contamination surveys, for contamination control between different access zones, for airborne radioactivity monitoring/sampling and for personnel monitoring shall also be described. 

Information shall be provided on the protective clothing and equipment routinely used at the facility, including respiratory protective equipment. 

Special equipment available for use in an emergency when high dose rates may prevail, and any special training of facility personnel in the use of this special equipment are described in the Emergency Plan (see para. A.2003). 

The nature and intensity of sources of radiation deriving from the operation of a nuclear power plant wiU depend on various factors, including the type of reactor, its design features and its operational history. The protection of workers from harmful effects of radiation should be ensured by means of an RPP estabUshed by the operating organization. 

The RPP should be based on a prior risk assessment in which the locations and magnitudes of all radiation hazards have been taken into account, and should cover  

The operating organization shall designate as a controlled area any area in which specific protective measures or safety provisions are or could be required for  

Paragraph 8.2 of Ref. [1] requires that the RPP cover the classification of areas and access control, including local information on actual dose rates and contamination levels. The regulatory body may issue guidance on the classification of controlled areas on the basis of the particular circumstances. 

In determining the boundaries of any controlled area, the magnitude of expected doses in normal operation, the likelihood and magnitude of potential exposures, and the nature and extent of the required protection and safety procedures, including the control of radioactive waste, should be taken into account. 

This section should describe the administrative organization, the equipment, instrumentation and facilities, and the procedures for the radiation protection programme. It should be demonstrated that, as recommended in para. 2.2 of Ref. [41], the plant radiation protection programme is based on a prior risk assessment that takes into account the location and magnitude of all radiation hazards, and covers  

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A.25. Organizational structure for radiation protection. The structure of the organization responsible for the implementation of the radiation protection programme, the procedures necessary for implementation of the programme, the effectiveness of the management and its commitment with respect to radiation protection, including apphcation of the optimization principle, should aU be assessed... 

The occupational radiation protection programme, including arrangements for monitoring of workers and the workplace, and the provision and maintenance of personal protective equipment and equipment for radiation detection ... 

The objectives of the Radiation Protection Programme (RPP) for the transport of radioactive material are ... 

After the text of this publication had been prepared, the IAEA issued Safety Standards Series No. RS-G-1.1, Occupational Radiation Protection, IAEA, Vienna (1999). This Safety Guide may provide additional guidance on the development and implementation of radiation protection programmes and the monitoring and assessing of radiation doses. 

While such doses would no longer be acceptable, the adequacy of the current radiation level limits, in terms of radiological safety, has been confirmed by a number of surveys where radiation exposure of transport workers has been determined [29-32] and by an assessment performed by the IAEA in 1985 [33]. However, it is recognized that the permitted radiation levels around packages and conveyances do not alone ensure acceptably low doses, and the Regulations also require the establishment of radiation protection programmes (para. 301) and the periodic assessment of radiation doses to persons due to the transport of radioactive material (para. 304). 

There was a provision concerning the radiation level at any normally occupied position in the case of road vehicles in the 1985 edition of the Regulations. This provision was deleted in the 1996 edition of the Regulations. It has effectively been superseded by the introduction of the concept of radiation protection programmes (see paras 301 and 305). 

Although not directly part of a radiation protection programme, limitations on stowage associated with the heat output from each package should be considered. The means for heat removal, both natural and mechanical, should be assessed for this purpose, and heat outputs for individual packages should be specified if necessary. 

Records of measurements taken during each voyage should be supplied to the competent authority on request. This is one method of ensuring that the radiation protection programme and any other controls have functioned adequately. 

Acknowledgements. This work was supported in part by contract BI6-158-I from the Radiation Protection Programme of the Commission of the European Communities. U.B. is a scientist official of Q5C R.I. is recipient of a fellowship from Fondazione Buzzati-Traverso and P.L. from Associatione Italiana Riceica sul Cancio. 

Radiation Protection Programme shall mean systematic arrangements which are aimed at providing adequate consideration of radiation protection measures. 

A Radiation Protection Programme shall be established for the transport of radioactive material. The nature and extent of the measures to be employed in the programme shall be related to the magnitude and likelihood of radiation exposures. The programme shall incorporate the requirements of paras 301, 303-305 and 311. Programme documents shall be available, on request, for inspection by the relevant competent authority. 

An enforcement policy recognizing this difference in risk for hot particle exposure situations was published in the Federal Register July 31, 1990, and as an enclosure to Information Notice 90-48. However, a rule is needed to codify the results of health effects research in this area and to establish a firm basis for licensees radiation protection programmes. The NRC is establishing a technical basis for the rule making through research teing performed by a National Laboratory and the NCRP. 

Chapter 12 presents the processes for normal operational dose assessment and radiation protection programme design features. 

Radiation monitoring this identifies the plant monitoring provisions throughout the lifetime. Details of site specific radiation protection programme are not included, as these will be subject to site licensee administrative arrangements and are not covered by the generic site PCSR. 

During operation, the Site Licensee will employ a comprehensive radiation protection programme (see Section 12.7). The APIOOO design has an installed system of area radiation and airborne activity monitoring instrumentation. A description of the radiation monitoring system (RMS) is presented in Chapter 11.5 of the EDCD (Reference 12.1). 

For all operational states and DBAs, adequate provision shall be made in the design, on the basis of a consistent radiation protection programme and in accordance with the radiation protection objective (see para. 205 of Ref. [1], quoted in para. 2.2), for shielding, ventilation, filtration and decay systems for radioactive material (such as delay tanks), and for monitoring instrumentation for radiation and airborne radioactive material inside and outside the controlled area. 

A radiation protection programme is developed and implemented Emergency procedures are established and implemented ... 

A radiation protection group shall be established to prepare and implement a radiation protection programme and to advise the reactor management and the operating organization on matters relating to radiation protection. This is discussed in paras 7.93-7.107. 

The radiation protection programme is subject to the requirements for occupational radiation protection (see Refs [12, 25]) and in particular shall include measures for ... 

All personnel at the facility shall be individually responsible for putting into practice the measures for exposure control in their areas of activity that are specified in the radiation protection programme. Consequently, particular emphasis shall be given to training all the facility s personnel to ensure that... 

All applicable recommendations of the regulatory body and the existing national legal provisions should, wherever practicable, be translated into specific provisions and procedures that individuals can apply, and should be incorporated into the radiation protection programme (RPP) and radioactive waste management programme (RWMP) of the plant. 

In accordance with Refs [2, 7], the management of the operating organization should be responsible for ensuring that appropriate radiation protection programmes... 

The present Safety Guide addresses the assessment of exposure due to intakes of radionuchdes in the workplace. Snch intakes can occur via a number of pathways whenever unsealed soirrces are present, and the monitoring of workers and the workplace in such situations is an integral part of ar occupational radiation protection programme. The assessment of exposure due to intakes depends critically upon knowledge of the biokinetics of the radionuclides, and the present Safety Guide reflects the major changes over the past decade in international practice in internal dose assessment. 

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