10 CFR 72.122, Overall Requirements

Overall requirements

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(a) Quality Standards. Structures, systems, and components important to safety must be designed, fabricated, erected, and tested to quality standards commensurate with the importance to safety of the function to be performed.

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(b) Protection against environmental conditions and natural phenomena. (1) Structures, systems, and components important to safety must be designed to accommodate the effects of, and to be compatible with, site characteristics and environmental conditions associated with normal operation, maintenance, and testing of the ISFSI or MRS and to withstand postulated accidents.

(2) Structures, systems, and components important to safety must be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, lighting, hurricanes, floods, tsunami, and seiches, without impairing their capability to perform safety functions. The design bases for these structures, systems, and components must reflect:

(i) Structures, systems, and components important to safety must be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, lightning, hurricanes, floods, tsunami, and seiches, without impairing their capability to perform their intended design functions. The design bases for these structures, systems, and components must reflect:

(A) Appropriate consideration of the most severe of the natural phenomena reported for the site and surrounding area, with appropriate margins to take into account the limitations of the data and the period of time in which the data have accumulated, and

(B) Appropriate combinations of the effects of normal and accident conditions and the effects of natural phenomena.

(ii) The ISFSI or MRS also should be designed to prevent massive collapse of building structures or the dropping of heavy objects as a result of building structural failure on the spent fuel, high-level radioactive waste, or reactor-related GTCC waste or on to structures, systems, and components important to safety.

(3) Capability must be provided for determining the intensity of natural phenomena that may occur for comparison with design bases of structures, systems, and components important to safety.

(4) If the ISFSI or MRS is located over an aquifer which is a major water resource, measures must be taken to preclude the transport of radioactive materials to the environment through this potential pathway.

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(c) Protection against fires and explosions. Structures, systems, and components important to safety must be designed and located so that they can continue to perform their safety functions effectively under credible fire and explosion exposure conditions. Noncombustible and heat-resistant materials must be used wherever practical throughout the ISFSI or MRS, particularly in locations vital to the control of radioactive materials and to the maintenance of safety control functions. Explosion and fire detection, alarm, and suppression systems shall be designed and provided with sufficient capacity and capability to minimize the adverse effects of fires and explosions on structures, systems, and components important to safety. The design of the ISFSI or MRS must include provisions to protect against adverse effects that might result from either the operation or the failure of the fire suppression system.

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(d) Sharing of structures, systems, and components. Structures, systems, and components important to safety must not be shared between an ISFSI or MRS and other facilities unless it is shown that such sharing will not impair the capability of either facility to perform its safety functions, including the ability to return to a safe condition in the event of an accident.

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(e) Proximity of sites. An ISFSI or MRS located near other nuclear facilities must be designed and operated to ensure that the cumulative effects of their combined operations will not constitute an unreasonable risk to the health and safety of the public.

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(f) Testing and maintenance of systems and components. Systems and components that are important to safety must be designed to permit inspection, maintenance, and testing.

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(g) Emergency capability. Structures, systems, and components important to safety must be designed for emergencies. The design must provide for accessibility to the equipment of onsite and available offsite emergency facilities and services such as hospitals, fire and police departments, ambulance service, and other emergency agencies.

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(h) Confinement barriers and systems. (1) The spent fuel cladding must be protected during storage against degradation that leads to gross ruptures or the fuel must be otherwise confined such that degradation of the fuel during storage will not pose operational safety problems with respect to its removal from storage. This may be accomplished by canning of consolidated fuel rods or unconsolidated assemblies or other means as appropriate.

(2) For underwater storage of spent fuel, high-level radioactive waste, or reactor-related GTCC waste in which the pool water serves as a shield and a confinement medium for radioactive materials, systems for maintaining water purity and the pool water level must be designed so that any abnormal operations or failure in those systems from any cause will not cause the water level to fall below safe limits. The design must preclude installations of drains, permanently connected systems, and other features that could, by abnormal operations or failure, cause a significant loss of water. Pool water level equipment must be provided to alarm in a continuously manned location if the water level in the storage pools falls below a predetermined level.

(3) Ventilation systems and off-gas systems must be provided where necessary to ensure the confinement of airborne radioactive particulate materials during normal or off-normal conditions.

(4) Storage confinement systems must have the capability for continuous monitoring in a manner such that the licensee will be able to determine when corrective action needs to be taken to maintain safe storage conditions. For dry spent fuel storage, periodic monitoring is sufficient provided that periodic monitoring is consistent with the dry spent fuel storage cask design requirements. The monitoring period must be based upon the spent fuel storage cask design requirements.

(5) The high-level radioactive waste and reactor-related GTCC waste must be packaged in a manner that allows handling and retrievability without the release of radioactive materials to the environment or radiation exposures in excess of part 20 limits. The package must be designed to confine the high-level radioactive waste for the duration of the license.

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(j) Control room or control area. A control room or control area, if appropriate for the ISFSI or MRS design, must be designed to permit occupancy and actions to be taken to monitor the ISFSI or MRS safely under normal conditions, and to provide safe control of the ISFSI or MRS under off-normal or accident conditions.

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(k) Utility or other services. (1) Each utility service system must be designed to meet emergency conditions. The design of utility services and distribution systems that are important to safety must include redundant systems to the extent necessary to maintain, with adequate capacity, the ability to perform safety functions assuming a single failure.

(2) Emergency utility services must be designed to permit testing of the functional operability and capacity, including the full operational sequence, of each system for transfer between normal and emergency supply sources; and to permit the operation of associated safety systems.

(3) Provisions must be made so that, in the event of a loss of the primary electric power source or circuit, reliable and timely emergency power will be provided to instruments, utility service systems, the central security alarm station, and operating systems, in amounts sufficient to allow safe storage conditions to be maintained and to permit continued functioning of all systems essential to safe storage.

(4) An ISFSI or MRS which is located on the site of another facility may share common utilities and services with such a facility and be physically connected with the other facility; however, the sharing of utilities and services or the physical connection must not significantly:

(i) Increase the probability or consequences of an accident or malfunction of components, structures, or systems that are important to safety; or

(ii) Reduce the margin of safety as defined in the basis for any technical specifications of either facility.

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(l) Retrievability. Storage systems must be designed to allow ready retrieval of spent fuel, high-level radioactive waste, and reactor-related GTCC waste for further processing or disposal.

Federal Register

, as amended at 64 FR 33184, June 22, 1999; 66 FR 51842, Oct. 11, 2001]

External Links

NRC website 10 CFR 72.122

v t e Code of Federal Regulations
Title 10 Part 72 - LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR- RELATED GREATER THAN CLASS C WASTE
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
1, General Provisions, Purpose 2, Scope 3, Definitions 4, Communications 5, Interpretations 6, License required; types of licenses 7, Specific exemptions 8, Denial of licensing by Agreement States 9, Information collection requirements: OMB approval 10, Employee protection 11, Completeness and accuracy of information 12, Deliberate misconduct 13, Applicability 16, License Application, Form, and Contents, Filing of application for specific license 18, Elimination of repetition 20, Public inspection of application 22, Contents of application: General and financial information 24, Contents of application: Technical information 26, Contents of application: Technical specifications 28, Contents of application: Applicant's technical qualifications 30, Financial assurance and recordkeeping for decommissioning 32, Emergency Plan 34, Environmental report 40, Issuance and Conditions of License, Issuance of license 42, Duration of license; renewal 44, License conditions 46, Public hearings 48, Changes, tests, and experiments 50, Transfer of license 52, Creditor regulations 54, Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas 56, Application for amendment of license 58, Issuance of amendment 60, Modification, revocation, and suspension of license 62, Backfitting 70, Records, Reports, Inspections, and Enforcement, Safety analysis report updating 72, Material balance, inventory, and records requirements for stored materials 74, Reports of accidental criticality or loss of special nuclear material 75, Reporting requirements for specific events and conditions 76, Material status reports 78, Nuclear material transaction reports 79, §72.79 Facility information and verification. 80, Other records and reports 82, Inspections and tests 84, Violations 86, Criminal penalties 90, Siting Evaluation Factors, General considerations 92, Design basis external natural events 94, Design basis external man-induced events 96, Siting limitations 98, Identifying regions around an ISFSI or MRS site 100, Defining potential effects of the ISFSI or MRS on the region 102, Geological and seismological characteristics for applications before October 16, 2003 and applications for other than dry cask modes of storage 103, Geological and seismological characteristics for applications for dry cask modes of storage on or after October 16, 2003 104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS 106, Controlled area of an ISFSI or MRS 108, Spent fuel or high-level radioactive waste transportation 120, General Design Criteria, General considerations 122, Overall requirements 124, Criteria for nuclear criticality safety 126, Criteria for radiological protection 128, Criteria for spent fuel, high-level radioactive waste, and other radioactive waste storage and handling 130, Criteria for decommissioning 140, Quality Assurance, Quality assurance requirements 142, Quality assurance organization 144, Quality assurance program 146, Design control 148, Procurement document control 150, Instructions, procedures, and drawings 152, Document control 154, Control of purchased material, equipment, and services 156, Identification and control of materials, parts, and components 158, Control of special processes 160, Licensee inspection 162, Test control 164, Control of measuring and test equipment 166, Handling, storage, and shipping control 168, Inspection, test, and operating status 170, Nonconforming materials, parts, or components 172, Corrective action 174, Quality assurance records 176, Audits 180, Physical Protection, Physical protection plan 182, Design for physical protection 184, Safeguards contingency plan 186, Change to physical security and safeguards contingency plans 190, Training and Certification of Personnel, Operator requirements 192, Operator training and certification program 194, Physical requirements 200, Provision of MRS Information to State Governments and Indian Tribes, Provision of MRS information 202, Participation in license reviews 204, Notice to States 206, Representation 210, General License for Storage of Spent Fuel at Power Reactor Sites, General license issued 212, Conditions of general license issued under § 72.210 214, List of approved spent fuel storage casks 216, 218, Termination of licenses 220, Violations 230, Approval of Spent Fuel Storage Casks, Procedures for spent fuel storage cask submittals further results Appendices:

10 CFR 72.122, Overall Requirements

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Federal Register

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