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14 декабря, 2021
Experience gained over the past years by the Bureau of Radiological Health and by various states has provided the technical basis for the establishment of surveillance programs in the environs of nuclear plants. The guidance for environmental surveillance of nuclear facilities provided by the Bureau of Radiological Health is applicable to those areas external to the facility’s site perimeter or fenced area, which is normally considered as the plant environs or off-site area. Accomplishment of the objectives of these programs assures continuing examination and evaluation of the environment needed for the continued health and safety of the public. To ensure compatability of the surveillance data from both federal and state programs, an analytical quality control service is available through the Bureau’s area laboratories. The prime objectives of environmental surveillance programs for nuclear power stations are to verify the adequacy of source control, to provide data to estimate population exposure, and to provide a source of data for public information. An environmental surveillance program should be conducted by the facility operator. As a minimum, surveillance activities by the health agency should provide adequate verification of the facility’s data. This procedure allows both the health agency and the operator to have confidence in the accuracy of the results.
The materials to be sampled, the frequency of sampling, and the type of analysis needed are all dependent upon the specific program objectives that have been established for the facility. The extent of surveillance required is dependent on the nuclear facility’s location (population density, meteorology, and other environmental factors), and the quantities and kinds of radioactive materials discharged. A review of the plant environment and the facility’s radioactive waste system should include an evaluation of the critical radionuclides anticipated in the normal discharges and the pathways through which they may disperse in the environment and thus expose the population to radiation. Because air and water are pathways through which radioactive contaminants are carried to other segments of the environment, analysis of radioactivity in these media is a basic requirement in the establishment of a surveillance program. Further, an investigation of the site environs is necessary to identify members of the public most likely to be exposed and the pathways of exposure. Exposure of this critical population group can result from direct external radiation and from intake of radioactive material into the body through ingestion and inhalation.
In initiating an environmental surveillance program, it is important that radiological measurements be made and data obtained through a preoperational survey of the plant environs. This survey will provide information related to the critical nuclides, pathways, and population groups that can be used to design the operational program. Additional information will be obtained that is useful for other purposes, among which are: (a) to provide a data base to be used in delineating any radioactive material released to the environment by the plant after initial start-up, (b) to demonstrate that the proposed surveillance system is adequate, (c) to give training and experience to the personnel conducting the survey, and (d) to provide a mechanism for gathering data for public information. Because waste discharges from a nuclear power plant operating under normal conditions should influence environmental radioactivity levels in only a limited area, preoperational samples should be taken beyond the plant’s influence for comparison with those taken near the site. This practice can be continued into the operating phase and a statistical comparison made in order to delineate possible contributions by the plant to environmental radioactivity levels. It has been normal practice for preoperational surveys to be conducted for a period of one year before the initial start-up of a nuclear installation. In those cases where personnel are inexperienced in surveillance operations and laboratory analysis of samples or special requirements are indicated, a longer period of time may be necessary in order to obtain reliable data for at least one year.
The data gathered by the environmental surveillance program during plant operation must provide the basis for source control and estimation of population dose. Complete liquid and gaseous radioactivity discharge data should be routinely provided to the health agency by the operator so that the relation between radioactive discharges and the environmental surveillance data can be established. Experience to date with nuclear power plants has shown that careful waste management, engineered safeguards, and proper operating procedures generally result in a radionuclide concentration in waste effluents ranging from 1 to 3 per cent of the aec’s licensed discharge limits (Blomeke & Harrington, 1968).
Detection of individual accidental releases in time to take protective action is not an objective of a routine operational environmental surveillance program. Although protective actions can appreciably reduce the dose received if initiated quickly, the indication of a need for such actions must come from the facility in question immediately following any accidental release and not several days or weeks later from routine environmental sampling. For this reason, adequate source monitoring and control must be in effect to detect immediately significant nonroutine releases of radioactivity. In the event of such a release, it is imperative that agencies responsible for public health be promptly notified so they can initiate emergency monitoring programs with the objective of ascertaining whether or not there is a need for protective actions. A special preplanned documented emergency monitoring system is required in order to be able to assess adequately any public health hazard in the event of a major accidental release of radioactivity to the off-site area.
The surveillance described here pertains to the operation of nuclear installations under normal operating conditions and is not intended to apply to an accident situation. The recommended general program shown on page 64 (Terrill et al., 1968; Weaver & Harward, 1967) serves as a guide for the development of an environmental monitoring program and is considered adequate from a public health standpoint. However, with the rapid expansion of the nuclear power industry, the number of individual facility monitoring programs will increase. Therefore, the Bureau of Radiological Health is updating these surveillance recommendations, on the basis of field studies which are being carried out through the Bureau’s area laboratories to obtain basic data needed to define upgraded surveillance requirements. Because of the planned increase in the nuclear power industry, it is important to develop a coordinated nationwide surveillance
Vectors or Indices |
Relative Frequency |
Analyses |
Sampling Locations |
Continuous composite or |
Gross beta and gamma |
Stream above and below the |
|
waters of the facility………… |
. weekly grab |
scans; periodic beta scintillation analysis for SH with frequency a function of the levels measured |
facility; reservoir, bay, lake — nearest shoreline; any nearby domestic water suppliers using the receiving waters as a raw water source |
Bottom sediments……………. |
. Semiannually |
Gross beta and gamma scans |
Near reactor’s outfall or above and below the outfall if the receiving water is a stream |
Ground water A………………. |
. As applicable (usually quarterly or annually) |
Gross beta and gamma scans |
Supplies within 5 mi. of th« facility |
Air |
|||
Inhalation……………………. |
. High-volume samples |
Gross beta and gamma scans |
Populated areas within 5-15 |
occasionally; low-volume samples daily or weekly |
of filters and cartridges |
mi. of the facility |
|
Submersion…………………. |
. Dosimeters changed every 28 days |
Integrated dose from noble gases by appropriate reader device |
|
Milk………………………………. |
. Monthly |
Gamma spectrum analysis for mI |
Dairy herds within 10-15 mi. of the facility |
Quarterly |
^Sr and “Sr or total Sr by beta analysis |
Dairy herds within 10-15 mi. of the facility |
|
Aquatic biota………………….. |
. Variable |
Gamma spectrum analysis for selected radio nuclides |
Near the reactor’s outfall or above and below if receiving water is a stream |
Food crops and other |
|||
vegetation……………………….. |
. Seasonal (before or at harvesting time) |
Gamma spectrum analysis |
Within a 10-15-mi. radius of the facility |
Soil………………………………… |
. Annually |
“Sr and “Cs or gross beta |
Prevailing downwind direction in nearest agricultural areas |
source: Terrill et al., 1968; Weaver & Harward, 1967. |