10 CFR 72.126 - Criteria for radiological protection.

§ 72.126 Criteria for radiological protection.

(a)Exposure control. Radiation protection systems must be provided for all areas and operations where onsite personnel may be exposed to radiation or airborne radioactive materials. Structures, systems, and components for which operation, maintenance, and required inspections may involve occupational exposure must be designed, fabricated, located, shielded, controlled, and tested so as to control external and internal radiation exposures to personnel. The design must include means to:

(1) Prevent the accumulation of radioactive material in those systems requiring access;

(2) Decontaminate those systems to which access is required;

(3) Control access to areas of potential contamination or high radiation within the ISFSI or MRS;

(4) Measure and control contamination of areas requiring access;

(5) Minimize the time required to perform work in the vicinity of radioactive components; for example, by providing sufficient space for ease of operation and designing equipment for ease of repair and replacement; and

(6) Shield personnel from radiation exposure.

(b)Radiological alarm systems. Radiological alarm systems must be provided in accessible work areas as appropriate to warn operating personnel of radiation and airborne radioactive material concentrations above a given setpoint and of concentrations of radioactive material in effluents above control limits. Radiation alarm systems must be designed with provisions for calibration and testing their operability.

(c)Effluent and direct radiation monitoring.

(1) As appropriate for the handling and storage system, effluent systems must be provided. Means for measuring the amount of radionuclides in effluents during normal operations and under accident conditions must be provided for these systems. A means of measuring the flow of the diluting medium, either air or water, must also be provided.

(2) Areas containing radioactive materials must be provided with systems for measuring the direct radiation levels in and around these areas.

(d)Effluent control. The ISFSI or MRS must be designed to provide means to limit to levels as low as is reasonably achievable the release of radioactive materials in effluents during normal operations; and control the release of radioactive materials under accident conditions. Analyses must be made to show that releases to the general environment during normal operations and anticipated occurrences will be within the exposure limit given in § 72.104. Analyses of design basis accidents must be made to show that releases to the general environment will be within the exposure limits given in § 72.106. Systems designed to monitor the release of radioactive materials must have means for calibration and testing their operability.

This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.

This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].

It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.

United States Code

§ 2021 - Cooperation with States

§ 2071 - Determination of other material as special nuclear material; Presidential assent; effective date

§ 2073 - Domestic distribution of special nuclear material

§ 2077 - Unauthorized dealings in special nuclear material

§ 2092 - License requirements for transfers

§ 2093 - Domestic distribution of source material

§ 2095 - Reports

§ 2099 - Prohibitions against issuance of license

§ 2111 - Domestic distribution

§ 2201 - General duties of Commission

§ 2232 - License applications

§ 2233 - Terms of licenses

§ 2234 - Inalienability of licenses

§ 2236 - Revocation of licenses

§ 2238 - Continued operation of facilities

§ 2239 - Hearings and judicial review

§ 2282 - Civil penalties

§ 4332 - Cooperation of agencies; reports; availability of information; recommendations; international and national coordination of efforts

§ 5841 - Establishment and transfers

§ 5842 - Licensing and related regulatory functions respecting selected Administration facilities

§ 5846 - Compliance with safety regulations

§ 5851 - Employee protection

§ 10101 - Definitions

§ 10102 - Separability

§ 10103 - Territories and possessions

§ 10104 - Ocean disposal

§ 10105 - Limitation on spending authority

§ 10106 - Protection of classified national security information

§ 10107 - Applicability to atomic energy defense activities

§ 10108 - Applicability to transportation

§ 10137 - Consultation with States and affected Indian tribes

§ 10151 - Findings and purposes

§ 10152 - Available capacity for interim storage of spent nuclear fuel

§ 10153 - Interim at-reactor storage

§ 10154 - Licensing of facility expansions and transshipments

§ 10155 - Storage of spent nuclear fuel

§ 10157 - Transportation

§ 10161 - Monitored retrievable storage

§ 10162 - Authorization of monitored retrievable storage

§ 10165 - Site selection

§ 10168 - Construction authorization

§ 10198 - Research and development on spent nuclear fuel

Statutes at Large

Title 10 published on 10-May-2017 03:48

The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR Part 72 after this date.

  • 2017-04-13; vol. 82 # 70 - Thursday, April 13, 2017
    1. 82 FR 17749 - List of Approved Spent Fuel Storage Casks: AREVA Inc., Standardized NUHOMS® Cask System, Certificate of Compliance No. 1004, Amendment No. 14, and Revision 1 of the Initial Certificate, Amendment Nos. 1 Through 11, and Amendment No. 13
      GPO FDSys XML | Text
      Direct final rule; confirmation of effective date.
      Effective Date: The effective date of April 25, 2017, for the direct final rule published January 25, 2017 (82 FR 8353), is confirmed.
      10 CFR Part 72


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