Specifications for radiation symbol/warning sign:

• The radiation symbol for radioactive sources other than medical diagnostic and industrial x-ray radiography equipment shall confirm to the specifications given hereunder;
• The relative dimensions of the trefoils and the central circle shall be as shown in Fig.1.
• The trefoils and the circle shall be of magenta colour.
• The background of the above symbol shall be yellow.
• The symbol should be accompanied by appropriate legend in English, Hindi and local language indicating radiation hazard and restricted entry, e.g. CAUTION – RADIOACTIVITY.
• Small objects, containing radioactive material may, however, have on them only the aforesaid trefoil symbol engraved in a conspicuous colour when their dimensions do not permit compliance with (d) above.
• The radiation symbol for radiation generating equipment such as medical diagnostic x-ray equipment, industrial x-ray radiography equipment and accelerators shall have a warning sign as illustrated in Fig.2 and the warning sign shall conform to the specifications given hereunder;

• The triangle shall be equilateral.
• The ratio of the outer to the inner sides of the triangle shall be 1.5.
• The area between the outer and inner triangle shall be in yellow colour on white background.
• The printing on the area between the outer and inner triangle and figure inside the inner triangle shall be bold, proportional and red in colour.
• The area between the outer and inner triangle should be accompanied by appropriate legend in English, Hindi and local language indicating radiation hazard and restricted entry.

In exercise of rule 15 of the Atomic Energy (Radiation Protection) Rules, 2004, the Chairman, Atomic Energy Regulatory Board, being the Competent Authority under the said rules, hereby issues an order prescribing the dose limits for exposures from ionising radiations for workers and the members of the public, which shall be adhered to. Dose Limits

General

• The limits on effective dose apply to the sum of effective doses from external as well as internal sources. The limits exclude the exposures due to natural background radiation and medical exposures.
• Calendar year shall be used for all prescribed dose limits.

• Occupational Dose Limits
• • Occupational Workers

  The occupational exposures of any worker shall be so controlled that the following limits are not exceeded:

  • an effective dose of 20 mSv/yr averaged over five consecutive years (calculated on a sliding scale of five years);
  • an effective dose of 30 mSv in any year;
  • an equivalent dose to the lens of the eye of 150 mSv in a year;
  • an equivalent dose to the extremities (hands and feet) of 500 mSv in a year and
  • an equivalent dose to the skin of 500 mSv in a year;
  • limits given above apply to female workers also. However, once pregnancy is declared the equivalent dose limit to embryo/fetus shall be 1 mSv for the remainder of the pregnancy.
  • Apprentices and Trainees

  The occupational exposure of apprentices and trainees between 16 and 18 years of age shall be so controlled that the following limits are not exceeded:

  
  
  • an effective dose of 6 mSv in a year;
  • an equivalent dose to the lens of the eye of 50 mSv in a year;
  • an equivalent dose to the extremities (hands and feet) of 150 mSv in a year and
  • an equivalent dose to the skin of 150 mSv in a year.
• Dose Limits for Members of the Public

• The estimated average doses to the relevant members of the public shall not exceed the following limits:

  
  
  • an effective dose of 1 mSv in a year;
  • an equivalent dose to the lens of the eye of 15 mSv in a year; and
  • an equivalent dose to the skin of 50 mSv in a year.

Rock phosphates imported in India by the fertilizer plants for production of phosphoric acid contain small concentrations of radioactive nuclides, viz., Uranium-238 and Radium-226. Phosphogypsum produced as byproduct during wet processing of imported rock phosphates contains activity concentration of U-238 typically in the range 0.1-0.2 Bq/g and Ra-226 typically in the range 0.5-1.3 Bq/g.

The subject of processing of imported rock phosphates and the use of phosphogypsum so produced in commercial applications like Building and Construction Materials and in Agriculture has been examined in the Atomic Energy Regulatory Board (AERB) from the radiological safety considerations and the following directives are issued.

• Analysis of Rock Phosphate and Phosphogypsum: All rock phosphate processing industries shall carry out analysis to determine U-238 and Ra-226 content in each imported consignment of rock phosphate as well as in the phosphogypsum produced from its processing and shall report the results to AERB on quarterly basis. This data will be reviewed in AERB for a period of about two years for deciding on the frequency of such analysis in future.
• Sale of Phosphogypsum by Fertilizer Plants: AERB approval is not required for selling phosphogypsum for its use in building and construction materials provided the activity concentration of Ra-226 in it is less than or equal to 1 Bq/g. [If Ra-226 concentration in phosphogypsum is more than 1Bq/g, it is to be mixed with other ingredients such that the Ra-226 activity concentration in bulk material is less than or equal to 1.0 Bq/g.]
• Manufacturing and Use of Phosphogypsum Panels and Blocks :AERB approval is not required for manufacturing and use of phosphogypsum panels or blocks provided they have Ra-226 activity less than 40 kBq/square metre area of any surface of the panels/blocks.
• Use in Agriculture :There is no restriction for use of phosphogypsum in agricultural applications from the radiological safety considerations.

All future plants/facilities including those under design shall be based on ICRP-60 which recommends that the dose constraint for optimisation should not exceed 20 mSv in a year for occupational exposures and 1 mSv in a year for the public. In compliance of this:

• The shieldings to be provided shall be such that the dose rates in full occupancy areas do not exceed 1 microSievert per hour (0.1 mRem per hour).
• The ventilation designs shall be such that the air concentration of the activities in full occupancy areas do not normally exceed 1/10 of the new derived air concentrations (DAC). The new DAC values can be obtained by dividing the annual limit on intake (ALI) values given in ICRP-61 by 2.4E3. (These ALI values for commonly encountered radionuclides are given below).
• All effluent discharges from a plant/facility/practice shall be so controlled that the exposure of the critical group does not exceed the public dose limit of 1 mSv in a year (excluding natural background and medical exposures) from all practices at the site.