Radiation Protection Regulations (SOR/2000-203)

Regulations are current to 2017-11-06 and last amended on 2017-09-22. Previous Versions

Requirement to Use Licensed Dosimetry Service

 Every licensee shall use a licensed dosimetry service to measure and monitor the doses of radiation received by and committed to nuclear energy workers who have a reasonable probability of receiving an effective dose greater than 5 mSv in a one-year dosimetry period.

Collection of Personal Information

 When, for purposes related to the administration of the Act and these Regulations, a licensee collects personal information, as defined in section 3 of the Privacy Act, that may be required to be disclosed to the Commission, another government institution or a dosimetry service, the licensee shall inform the person to whom the information relates of the purpose for which it is being collected.

Nuclear Energy Workers

 Every nuclear energy worker shall, on request by the licensee, inform the licensee of the worker’s

  • (a) given names, surname and any previous surname;

  • (b) Social Insurance Number;

  • (c) sex;

  • (d) date, province and country of birth; and

  • (e) dose record for the current one-year and five-year dosimetry periods.

  • SOR/2007-208, s. 7(E).

Pregnant Nuclear Energy Workers

  •  (1) Every nuclear energy worker who becomes aware that she is pregnant shall immediately inform the licensee in writing.

  • (2) On being informed by a nuclear energy worker that she is pregnant, the licensee shall, in order to comply with section 13, make any accommodation that will not occasion costs or business inconvenience constituting undue hardship to the licensee.

  • SOR/2007-208, s. 8(F).

Radiation Dose Limits

Interpretation

  •  (1) The definitions in this subsection apply in section 13.

    ALI

    ALI or annual limit on intake means the activity, in becquerel, of a radionuclide that will deliver an effective dose of 20 mSv during the 50-year period after the radionuclide is taken into the body of a person 18 years old or older or during the period beginning at intake and ending at age 70 after it is taken into the body of a person less than 18 years old. (LAI ou limite annuelle d’incorporation)

    E

    E means the portion of the effective dose, in millisievert

    • (a) received by a person from sources outside the body; and

    • (b) received by and committed to the person from sources inside the body, measured directly or from excreta. (E)

    I

    I means the activity, in becquerel, of any radionuclide that is taken into the body, excluding the radon progeny and the activity of other radionuclides accounted for in the determination of E. (I)

    Rn

    Rn means the average annual concentration in the air, in Bq per m3, of radon 222 that is attributable to a licensed activity. (Rn)

    RnP

    RnP means the exposure to radon progeny in working level months. (RnP)

    Σ I/ALI

    Σ I/ALI means the sum of the ratios of I to the corresponding ALI. (Σ I/LAI)

  • (2) For the purposes of sections 13 and 14, doses of radiation include those received from X-rays or other man-made sources of radiation.

Effective Dose Limits

  •  (1) Every licensee shall ensure that the effective dose received by and committed to a person described in column 1 of an item of the table to this subsection, during the period set out in column 2 of that item, does not exceed the effective dose set out in column 3 of that item.

    TABLE

    Column 1Column 2Column 3
    ItemPersonPeriodEffective Dose (mSv)
    1Nuclear energy worker, including a pregnant nuclear energy worker(a) One-year dosimetry period50
    (b) Five-year dosimetry period100
    2Pregnant nuclear energy workerBalance of the pregnancy4
    3A person who is not a nuclear energy workerOne calendar year1
  • (2) For the purpose of item 1 of the table to subsection (1), the effective dose shall be calculated using the following formula and expressed in millisievert:

    E + 5RnP + 20 Σ I ÷ ALI

  • (3) For the purpose of item 2 of the table to subsection (1), the effective dose shall be calculated using the following formula and expressed in millisievert:

    E + 20 Σ I ÷ ALI

  • (4) For the purpose of item 3 of the table to subsection (1), the effective dose shall be calculated using either of the following formulas and expressed in millisievert:

    E + Rn ÷ 60 + 20 Σ I ÷ ALI

    E + 4RnP + 20 Σ I ÷ ALI

  • (5) For the purpose of subsection (1), where the end of a dosimeter-wearing period or a bioassay-sampling period does not coincide with the end of a dosimetry period set out in column 2 of the table to that subsection, the licensee may extend or reduce the dosimetry period to a maximum of two weeks so that the end of the dosimetry period coincides with the end of the dosimeter-wearing period or biossay-sampling period, as the case may be.

Equivalent Dose Limits

  •  (1) Every licensee shall ensure that the equivalent dose received by and committed to an organ or tissue set out in column 1 of an item of the table to this subsection, of a person described in column 2 of that item, during the period set out in column 3 of that item, does not exceed the equivalent dose set out in column 4 of that item.

    TABLE

    Column 1Column 2Column 3Column 4
    ItemOrgan or TissuePersonPeriodEquivalent Dose (mSv)
    1Lens of an eye(a) Nuclear energy workerOne-year dosimetry period150
    (b) Any other personOne calendar year15
    2Skin(a) Nuclear energy workerOne-year dosimetry period500
    (b) Any other personOne calendar year50
    3Hands and feet(a) Nuclear energy workerOne-year dosimetry period500
    (b) Any other personOne calendar year50
  • (2) For the purpose of subsection (1), where a dosimeter-wearing period or a bioassay-sampling period extends beyond the end of a dosimetry period set out in column 3 of the table to that subsection, the period is extended to the end of the dosimeter-wearing or bioassay-sampling period or by two weeks, whichever extension is shorter.

  • (3) When skin is unevenly irradiated, the equivalent dose received by the skin is the average equivalent dose over the 1 cm2 area that received the highest equivalent dose.

 
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