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ANS-57.1, Design Requirements for Light Water Reactor Fuel Handling Systems

Scope: This standard sets forth the required functions of fuel handling systems at light water reactor nuclear power plants. It provides minimum design requirements for equipment and tools to handle nuclear fuel and control components safely.

ANS-57.2, Design Requirements for Light Water Reactor Used Fuel Storage Facilities at Nuclear Power Plants

Scope: This standard presents necessary design requirements for facilities at nuclear power plants for the pool storage and preparation for shipment of spent fuel from light-water moderated and cooled nuclear power stations, including consideration of the impact of high burn-up fuels. It contains requirements for the design of the following: (1) Fuel storage pool (2) Fuel storage racks (3) Pool makeup, instrumentation and cleanup systems (4) Pool structure and integrity (5) Radiation shielding (6) Residual heat removal (7) Ventilation, filtration and radiation monitoring systems (8) Shipping cask handling and decontamination (9) Building structure and integrity (10) Fire protection and communication Design requirements for spent fuel storage in an Independent Spent Fuel Storage Installation (ISFSI) subsequent to such initial pool storage are covered in ANSI/ANS Standard 57.7.

ANS-57.3, Design Requirements for New Fuel Storage Facilities at LWR Plants

Scope: This standard defines the required functions of wet or dry storage facilities for new fuel, including high burn-up fuel, at light water reactor nuclear power plants. It provides minimum design requirements for safe storage of new nuclear fuel and control components at such plants. The fuel storage facilities covered by this standard are used for receiving, inspecting and storing fuel containing new and recycled uranium and mixed oxides. The basis of this standard is that the intended function of the facilities will be performed in an efficient and economical manner to (a) preclude criticality, (b) ensure protection to new fuel assemblies, control components, plant personnel, and the public, and (c) maintain radiation exposures as low as reasonably achievable.

ANS-57.5, Light Water Reactors Fuel Assembly Mechanical Design and Evaluation

Scope: This standard sets forth a series of design conditions and functional requirements for the design of fuel assemblies for light water cooled commercial power reactors. It includes specific requirements for design, as well as design criteria to ensure adequate fuel assembly performance. The standard establishes a procedure for performing an evaluation of the mechanical design of fuel assemblies. It does not address the various aspects of neutronic or thermal-hydraulic performance except where these factors impose loads or constraints on the mechanical design of the fuel assemblies.

ANS-57.8, Fuel Assembly Identification

Scope: This standard describes requirements for the unique identification of fuel assemblies utilized in nuclear power plants. It defines the characters and proposed sequence to be used in assigning identification to fuel assemblies. This standard was developed primarily for commercial light-water reactor fuel, but may be used for any reactor fuel contained in discrete fuel assemblies that can be identified with a serial number as specified by this standard. Additionally, this standard describes requirements for a matrix system for identification in mapping the location of fuel rods within a fuel assembly. The matrix system establishes unique x-y coordinates for each possible rod location.

ANS-57.10, Design Criteria for Consolidation of LWR Spent Fuel

Scope: This standard provides design criteria for the process of consolidating LWR spent nuclear fuel in either a wet or a dry environment. It addresses processes for consolidating fuel either horizontally or vertically. The standard sets forth requirements for utilizing equipment and systems to perform consolidation, handle fuel rods and nonfuel-bearing components, and handle broken fuel rods. This standard also contains requirements for facility or installation interfaces, nuclear safety, structural design, thermal design, accountability, safeguards, decommissioning, and quality assurance.

Last updated July 22, 2014, 3:00pm CDT.

 
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