10 CFR 72.236 - Specific requirements for spent fuel storage cask approval and fabrication.

§ 72.236 Specific requirements for spent fuel storage cask approval and fabrication.

The certificate holder and applicant for a CoC shall ensure that the requirements of this section are met.

(a) Specifications must be provided for the spent fuel to be stored in the spent fuel storage cask, such as, but not limited to, type of spent fuel (i.e., BWR, PWR, both), maximum allowable enrichment of the fuel prior to any irradiation, burn-up (i.e., megawatt-days/MTU), minimum acceptable cooling time of the spent fuel prior to storage in the spent fuel storage cask, maximum heat designed to be dissipated, maximum spent fuel loading limit, condition of the spent fuel (i.e., intact assembly or consolidated fuel rods), the inerting atmosphere requirements.

(b) Design bases and design criteria must be provided for structures, systems, and components important to safety.

(c) The spent fuel storage cask must be designed and fabricated so that the spent fuel is maintained in a subcritical condition under credible conditions.

(d) Radiation shielding and confinement features must be provided sufficient to meet the requirements in §§ 72.104 and 72.106.

(e) The spent fuel storage cask must be designed to provide redundant sealing of confinement systems.

(f) The spent fuel storage cask must be designed to provide adequate heat removal capacity without active cooling systems.

(g) The spent fuel storage cask must be designed to store the spent fuel safely for the term proposed in the application, and permit maintenance as required.

(h) The spent fuel storage cask must be compatible with wet or dry spent fuel loading and unloading facilities.

(i) The spent fuel storage cask must be designed to facilitate decontamination to the extent practicable.

(j) The spent fuel storage cask must be inspected to ascertain that there are no cracks, pinholes, uncontrolled voids, or other defects that could significantly reduce its confinement effectiveness.

(k) The spent fuel storage cask must be conspicuously and durably marked with -

(1) A model number;

(2) A unique identification number; and

(3) An empty weight.

(l) The spent fuel storage cask and its systems important to safety must be evaluated, by appropriate tests or by other means acceptable to the NRC, to demonstrate that they will reasonably maintain confinement of radioactive material under normal, off-normal, and credible accident conditions.

(m) To the extent practicable in the design of spent fuel storage casks, consideration should be given to compatibility with removal of the stored spent fuel from a reactor site, transportation, and ultimate disposition by the

Department of Energy

(n) Safeguards Information shall be protected against unauthorized disclosure in accordance with the requirements of § 73.21 and the requirements of § 73.22 or § 73.23 of this chapter, as applicable.

[ 64 FR 56126, Oct. 15, 1999, as amended at 65 FR 50617, Aug. 21, 2000; 73 FR 63573, Oct. 24, 2008; 76 FR 8891, Feb. 16, 2011]

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 09-Nov-2018 03:26

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

  • 2018-11-21; vol. 83 # 225 - Wednesday, November 21, 2018
    1. 83 FR 58721 - Miscellaneous Corrections—Organizational Changes
      GPO FDSys XML | Text
      Final rule.
      This final rule is effective on December 21, 2018.
      10 CFR Parts 37, 40, 70, 71, 72, 73, 76, and 95


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