1、ANSVANS-57.1-1992 I I design requirements for light water reactor fuel handling systems This standard has been reviewed and reaffirmed by the ANS Nuclear Facilities Standards Committee (NFSC) with the recognition that it may reference other standards and documents that may have been superceded or wi
2、thdrawn The requirements of this document will be met by using the version of the standards and documents referenced herein It is the responsibility of the user to review each of the references and to determine whether the use of the onginal references or more recent versions is appropriate for lhe
3、facility Variations from the standards and documents referenced in this standard should be evaluated and documented This standard doec no! necessaniy refiect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance Users should consider the use of these
4、 industry initiatives in the application of this standard f This Standard has been reviewed and reaffirmed by the ANS Nuclear Facilities Standards Committee (NFSC) with the recognition that it may reference other standards and documents that may have been superceded Or withdrawn. The requirements of
5、 this document will be met by using the VerCiOn of the standards and documents referenced herein. It is the responsibility of the user to review each of the references and to determine whether the use of the original referencec or more recent versions is appropriate for the facility. Variations from
6、 the standards and documents referenced in this standard should be evaluated and documented. This standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance. USE should consider the use of these industry initiatives i
7、n the application of this standard. ANSVANS-57.1-1992 American National Standard Design Requirements for Light Water Reactor Fuel Handling Systems Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-57.1 Published by the American Nuclea
8、r Society 555 North Kensington Avenue La Grange Park, Illinois 60525 USA Approved July 28, 1992 by the American National Standards Institute, Inc. American National Standard standard has been achieved. Designation of this document as an American National Standard attests that the principles of openn
9、ess and due process have been followed in the approval procedure and that a consensus of those directly and materially affected by the This standard was developed under the procedures of the Standards Committee of the American Nuclear Society; these procedures are accredited by the American National
10、 Standards Institute, Inc., as meeting the criteria for American National Standards. The consensus committee that approved the standard was balanced to ensure that competent, concerned, and varied interests have had an opportunity to participate. An American National Standard is intended to aid indu
11、stry, consumers, govern- mental agencies, and general interest groups. Its use is entirely voluntary. The existence of an American National Standard, in and of itself, does not preclude anyone from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to th
12、e standard. By publication of this standard, the American Nuclear Society does not insure anyone utilizing the standard against liability allegedly arising from or after its use. The content of this standard reflects acceptable practice at the time of its approval and publication. Changes, if any, o
13、ccurring through developments in the state of the art, may be considered at the time that the standard is subjected to periodic review. It may be reaffirmed, revised, or withdrawn at any time in accordance with established procedures. Users of this standard are cautioned to determine the validity of
14、 copies in their possession and to establish that they are of the latest issue. The American Nuclear Society accepts no responsibility for interpretations of this standard made by any individual or by any ad hoc group of individuals. Requests for interpretation should be sent to the Standards Depart
15、ment at Society Headquarters. Action will be taken to provide appropriate response in accordance with established procedures that ensure consensus on the interpretation. Comments on this standard are encouraged and should be sent to Society Headquarters. Published by American Nuclear Society 555 Nor
16、th Kensington Avenue, La Grange Park, Illinois 60525 USA Copyright O 1993 by American Nuclear Society. Any part of this standard may be quoted. Credit lines should read “Extracted from American National Standard ANSUANS-67.1-1992 with permission of the publisher, the American Nuclear Society.“ Repro
17、duction prohibited under copyright convention unless written permission is granted by the American Nuclear Society. Printed in the United States of America (This foreword is not part of American National Standard Design Requirements for Light Water Reactor Fuel Handling Systems, ANSUANS-57.1-1992.)
18、This standard provides minimum design requirements for the designer of fuel handling equipment for water-cooled nuclear power plants. It sets forth design requirements that can assist in design and licensing efforts. It does not, however, relieve the designer of the responsibility for compliance wit
19、h any specific codes referenced herein. The designer is also reminded of U.S. Nuclear Regulatory Commission (MEC) Regulatory Guides that contain information that should be referred to in designing systems and components. The standard was developed under sponsorship of the American Nuclear Society an
20、d was first drafted in 1975. In this revision, it has been updated to reflect current criticality analysis standards and to address the potential for fuel handling systems to handle consolidated spent fuel. This standard was developed by Working Group ANS-57.1 of the Standards Committee of the Ameri
21、can Nuclear Society. The Working Group had the participa- tion of the following members during the period it revised and approved the standard: M. J. Akins, Chairman, GilbertlCommonwealth, Inc. J. A. Nevshemal, To transporting on-site and loading fuel assemblies containing new and recycled uranium o
22、r irradiated fuel Ad control components in the reactor; removing from the reactor, transporting to storage, and inspecting irradiated fuel, trans- porting irradiated fuel assemblies to rod consoli- dation equipment within a spent fuel or cask handling pool; transporting rod consolidation canisters t
23、o storage; and loading casks for ship- ment of irradiated fuel from or storage on the site. Rod consolidation is covered in American National Standard Design Criteria for Consolidation of LWR Spent Fuel, ANSUANS-57.10-1987 i. 1.4 Application of Codes and Standards. The structural members and mechani
24、cal and electrical systems of the fuel handling equipment shall be Numbers in brackets refer to corresponding numbers in Section 7, References. designed to meet applicable commercial codes and standards for fabrication and assembly except as specifically supplemented in Section 6, Design Requirement
25、s, of this standard. 2. Definitions auxiliary fuel handling crane. A crane used for handling equipment, fuel units, and new fuel shipping containers. commercial codes and standards. Standards that would be used in the design of conventional or commercial industrial components or sub- components. Exa
26、mples of commercial standards include the following: Power Piping, ANSI/ASME-B31.1-1989; ANSUASME Boiler and Pressure Vessel Code-1992, Section VIII, “Pressure Vessels,“ Division 1; Valves-Flanged, Threaded and Welding End, ANSUASME B16.34-1988; Overhead Hoists, ANSUASME- B30.16-1987; and “Specifica
27、tion for Electric Overhead Traveling Cranes,“ CMAA-70-1988. control components. Items included within the reactor vessel that control flow or reactivity and are handled or shifted in position during, when preparing for, and when recovering from fuel loading or refueling. Examples are control rods, f
28、low limiting orifices, and burnable poison rods. control component change mechanism. Handling equipment used to move control components from one fuel assembly or core location to another or to a temporary storage locations. failed fuel. Fuel with a perforation of or a defect in the fuel cladding or
29、any distortion or break causing a structural change that requires use of abnormal fuel unit handling procedures or equipment, premature replacement of a fuel assembly, replacement of its component parts, or restrictions on plant operation. fuel handling machine. Any equipment oper- ating over the sp
30、ent fuel pool designed for han- dling fuel units and control components. 1 American National Standard ANSUANS-67.1-1992 fuel handling system. Handling equipment used for receiving and inspecting new fuel and fuel containing recycled uranium or irradiated fuel and control components in the reactor; a
31、nd removing from the reactor, transporting to stor- age, and inspecting irradiated fuel and loading casks for shipment of irradiated fuel from or storage on the site. fuel preparation machine. A device consisting of a work platform, frame, and movable carriage used for stripping reusable channels fr
32、om spent fuel and for rechanneling new fuel in boiling water reactors (BWRs). It is normally mounted on the wall of the spent fuel pool. fuel rod. Those items of a fuel assembly that are long, thin-walled tubes closed by end caps. A fuel rod may contain fuel (uranium, plutonium, and fission products
33、) and nonfuel material (springs, inert gas, and so forth). fuel transfer mechanism. Handling equipment used to move fuel units between the spent fuel pool and the reactor area. fuel unit. An item to be handled that contains fuel rods. It can be a fuel assembly, canned spent fuel assembly, or a canis
34、ter of consolidated fuel rods. grapple. The action of making an attachment or the device making the attachment to a fuel unit or control component. gripper. The device used for engaging a fuel unit or control component. handling tools. Portable, manually or power- operated devices used for handling
35、or performing operations on fuel units or control components. latching or engaging. Physically attaching a tool or grapple to a fuel unit or control component in a manner to preclude accidental release. new fuel elevator. Equipment, usually installed in the spent fuel pool, to allow new fuel to be i
36、ntroduced from a shipping container or new fuel storage racks, and lowered for transfer to the spent fuel storage racks or transfer canal. pool. A single isolable body of water with a free surface. Examples are the spent fuel storage pool, the cask handling pool, the fuel transfer canal, and reactor
37、 refueling cavity (or well). raising or lowering (hoisting). Motion in a vertical direction. rechanneling. Removal and replacement of fuel channels for BWR fuel assemblies. redundant system. A system that independently duplicates the primary fundion of another system. refueling machine. Any equipmen
38、t operating over the reactor cavity (or well) and fuel transfer canal and designed for handling fuel units and control components. rotation. Angular motion about a fixed axis. safe shutdown earthquake (SSE). The earth- quake based on an evaluation of the maximum earthquake potential considering the
39、regional and local geology and seismology and specific charac- teristics of local subsurface material. It is the earthquake that produces the maximum vibratory ground motion for which structures, systems, and components are designed to remain functional. safety classification. Components shall be cl
40、assified as Safety Class 2, Safety Class 3, or as Non-Nuclear Safety (NNS) in accordance with criteria set forth in American National Standards Nuclear Safety Criteria for the Design of Station- ary Pressurized Water Reactor Plants, ANSIANS- 51.1-1983(R1988) and Nuclear Safety Criteria for the Desig
41、n of Stationary Boiling Water Reactor single system may have components in more than one class. Plants, ANSI/ANS-52.1-1983(R1988) 2,3. A seismic category I. The seismic classification of structures, systems, and components that are required to remain functional during and the word “should is used to
42、 denote a recommendation; and the word “may“ to denote permission, neither a requirement nor recommendation. To comply with this stan- dard, the design shall conform to its requirements but not necessarily with its recommendations. translation. Motion in a horizontal. plane. upender. Handling equipm
43、ent rotating about a futed horizontal axis used to move fuel units from a vertical to other than a vertical position and vice versa. 2 American National Standard ANSUANS-57.1-1992 3. System Safety Functions The function of the fuel handling system is to move new and irradiated fuel within the plant.
44、 The safety functions of the fuel handling system are to 3.1 Prevent Criticality. This is accomplished by component design and configuration. 3.2 Prevent Cladding Breach of Irradiated Fuel. This is accomplished by system design, configuration, and operational controls. 3.3 Limit Radiation Exposure.
45、This is accom- plished by system design, configuration, and operational controls. 4. System Definition The fuel handling system is functionally separat- ed into five subsystem: handling equipment (generally denoting installed components), han- dling tools (items more readily portable than handling e
46、quipment), inspection equipment, temporary storage equipment, and the trankfer tube assembly. 4.1 Handling Equipment 4.1.1 Subsystem Description. For the pur- poses of this standard, handling equipment is normally power-operated equipment designed to handle fuel units and control components. 4.1.2 S
47、ubsystem Components. The han- dling equipment subsystem includes, but is not limited to, the following: (1) Fuel handling machine. (2) New fuel elevator. (3) Auxiliary fuel handling crane. (4) Fuel transfer mechanism (includes drive and retrieval mechanisms). (5) Upenders. (6) Refueling machine. (7)
48、 Control component change mechanism. (8) Fuel preparation machine. 4.2 Handling Tools 4.2.1 Subsystem Description. Handling tools are portable, manually or power-operated devices used for handling or performing opera- tions on fuel units or control components. 4.2.2 Subsystem Components. Components
49、of the handling tools subsystem include, but are not limited to, the following: (1) Individual fuel rod handling tool. (2) Fuel preparation equipment. (3) Fuel assembly handling tool. (4) Control component handling tool. (5) Fuel rod consolidation canister handling tool. 4.3 Inspection Equipment 4.3.1 Subsystem Description. Inspection equipment includes equipment used to directly or remotely inspect fuel units and control com- ponents by visual or mechanical methods. 4.3.2 Subsystem Components. Components of the inspection equipment subsystem include, but are not limited to, the followin
