ANSI ANS 57.3-2018 Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants.pdf

《ANSI ANS 57.3-2018 Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants.pdf》由会员分享，可在线阅读，更多相关《ANSI ANS 57.3-2018 Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants.pdf（20页珍藏版）》请在麦多课文档分享上搜索。

1、An American National StandardPublished by the American Nuclear Society 555 N. Kensington AveLa Grange Park, IL 60526ANSI/ANS-57.3-2018Design Requirements for New Fuel Storage Facilities at Light Water Reactor PlantsANSI/ANS-57.3-2018ANSI/ANS-57.3-2018 American National Standard Design Requirements f

2、or New Fuel Storage Facilities at Light Water Reactor Plants Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-57.3 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Approved Febr

3、uary 27, 2018 by the American National Standards Institute, Inc. American National Standard ANSI/ANS-57.3-2018 American National Standard Designation of this document as an American National Standard attests that the principles of openness and due process have been followed in the approval procedure

4、 and that a consensus of those directly and materially affected by the standard has been achieved. This standard was developed under the procedures of the Standards Committee of the American Nuclear Society; these procedures are accredited by the American National Standards Institute, Inc., as meeti

5、ng 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 industry, consumers, governmental agenci

6、es, 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 the standard. By publication of this sta

7、ndard, 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, occurring through developments in the s

8、tate 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 copies in their possession and to est

9、ablish 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. Inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” an

10、d “may,” respectively) should be sent to the Scientific Publications and Standards Department at Society Headquarters. Action will be taken to provide appropriate response in accordance with established procedures that ensure consensus. Comments on this standard are encouraged and should be sent to

11、Society Headquarters. Published by American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA This document is copyright protected. Copyright 2018 by American Nuclear Society. All rights reserved. Any part of this standard may be quoted. Credit lines should read “Extract

12、ed from American National Standard ANSI/ANS-57.3-2018 with permission of the publisher, the American Nuclear Society.” Reproduction prohibited under copyright convention unless written permission is granted by the American Nuclear Society. Printed in the United States of America American National St

13、andard ANSI/ANS-57.3-2018 Inquiry Requests The American Nuclear Society (ANS) Standards Committee will provide responses to inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and “may,” respectively) in American National Standards that are developed

14、 and approved by ANS. Responses to inquiries will be provided according to the Policy Manual for the ANS Standards Committee. Nonrelevant inquiries or those concerning unrelated subjects will be returned with appropriate explanation. ANS does not develop case interpretations of requirements in a sta

15、ndard that are applicable to a specific design, operation, facility, or other unique situation only and therefore is not intended for generic application. Responses to inquiries on standards are published in ANSs magazine, Nuclear News, and are available publicly on the ANS website or by contacting

16、the Scientific Publications and Standards Department. Inquiry Format Inquiry requests shall include the following: (1) the name, company name if applicable, mailing address, and telephone number of the inquirer; (2) reference to the applicable standard edition, section, paragraph, figure, and/or tab

17、le; (3) the purpose(s) of the inquiry; (4) the inquiry stated in a clear, concise manner; (5) a proposed reply, if the inquirer is in a position to offer one. Inquiries should be addressed to: American Nuclear Society Scientific Publications and Standards Department 555 N. Kensington Avenue La Grang

18、e Park, IL 60526 or standardsans.org American National Standard ANSI/ANS-57.3-2018 American National Standard ANSI/ANS-57.3-2018 i Foreword (This foreword is not a part of American National Standard “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants,” ANSI/ANS-57.3-20

19、18, but is included for informational purposes.) This standard establishes minimum design requirements for the designer of new fuel dry storage facilities at water-cooled nuclear power plants. It provides general guidelines and specific design parameters that could assist in both the design and lice

20、nsing efforts if used. However, the designer is not relieved of the responsibility for complying with specific construction codes referenced herein. U.S. Nuclear Regulatory Commission regulations and guidance exist that contain information useful in designing systems and components. This standard wa

21、s developed under sponsorship of the American Nuclear Society and was first approved in 1983. In this revision, there have been some significant changes and some reorganization. Of note are simplification of the sections on seismic events and criticality. A new section on quality assurance was added

22、. Also, this standard was revised to address only dry storage of new fuel. Storage of new fuel in a spent fuel pool (wet storage) is covered by ANS-57.2. This standard was prepared by the ANS-57.3 Working Group of the American Nuclear Society Standards Committee. The ANS-57.3 Working Group had the f

23、ollowing membership during its work on this standard: R. Browder (Chair), Duke Energy B. Gutherman (Vice Chair), Gutherman Technical Services, LLC T. N. Ake, AREVA Federal Services, LLC M. J. Atkins, Worley Parson (semi-retired) D. W. Lewis, WECTEC C. Lobscheid, Advent Engineering Services, Inc. J.

24、V. Massey, California Maritime Academy (retired) M. W. Peres, Fluor Enterprises, Inc. M. P. Sanders, Westinghouse Electric Company, LLC M. E. Stasko, Duke Energy The New and Used Fuel (Design Only) Subcommittee had the following membership at the time of its approval of this standard: R. Browder, Du

25、ke Energy M. W. Peres, Fluor Enterprises, Inc. The Fuel, Waste, and Decommissioning Consensus Committee (FWDCC) had the following membership at the time of its approval of this standard: D. Hillyer (Chair), Energy Solutions J. F. Lucchini (Vice Chair), Los Alamos National Laboratory S. Bader, AREVA

26、Federal Services, LLC J. Brault, Individual D. R. Eggett, Individual H. Felsher, U.S. Nuclear Regulatory Commission J. Jansen Vehec, Individual D. W. Lewis, WECTEC C. Miller, Pacific Gas (b) ensure protection of new fuel assemblies, control components, plant personnel, and the public; and (c) mainta

27、in radiation exposures As Low As Reasonably Achievable (ALARA). Storage of new fuel assemblies in a spent fuel pool is covered in ANS-57.2-1983 (withdrawn) 1.2)2 Acronyms and definitions 2.1 Acronyms ALARA: As Low As Reasonably Achievable SSCs: structures, systems, and components SSE: safe shutdown

28、earthquake 2.2 Shall, should, and may shall, should, and may: The word “shall” is used to denote a requirement; the word “should” is used to denote a recommendation; and the word “may” is used to denote permission, neither a requirement nor a recommendation. 2.3 Definitions cell: A unit for storage

29、of an individual fuel assembly. It is a subassembly of a storage rack. 1)The current standard, ANSI/ANS-57.3-2018, is hereinafter referred to as “this standard.” 2)Numbers in brackets refer to corresponding numbers in Sec. 7, “References.” American National Standard ANSI/ANS-57.3-2018 2 control comp

30、onents: Components that control coolant flow or reactivity and may be handled or shifted in position during fuel loading or refueling. Examples are control rods, flow-limiting components, and burnable absorbers. fuel handling equipment: Equipment used for moving new fuel during receipt and inspectio

31、n, transporting to storage in-plant, and loading this fuel and control components in the reactor. latching: Physically attaching a tool to a fuel assembly or control component in such a manner as to preclude accidental release. mixed-oxide (MOX) fuel: A type of nuclear fuel that contains plutonium o

32、xide mixed with uranium oxide. natural phenomena: Environmental conditions external to a plant that are not manmade, some examples of which are earthquakes, tornadoes, flooding, lightning, hurricanes, snow, and ice. (Natural phenomena accommodated by nuclear power plant design criteria are termed “n

33、atural hazards.”) new fuel: A nuclear fuel assembly that has not been used for power generation. new fuel elevator: Equipment usually installed in the spent fuel pool or fuel transfer canal to allow new fuel, from either a shipping container, a new fuel inspection stand, or the new fuel storage rack

34、s, to be lowered for handling by the fuel handling equipment. new fuel storage rack enclosure: The boundary structures of the new fuel storage facility that protect the new fuel from the environment and from damage, theft, and sabotage. Such an enclosure may consist of a vault around the racks, a co

35、vered storage room or an open storage pit housed in a building, or an entire building in which the new fuel is being stored. optimal (optimum) moderation: The moderation condition that yields the highest effective neutron multiplication factor. rack: A structure consisting of an assembly of cells. s

36、afe shutdown earthquake (SSE): The earthquake that is based upon an evaluation of the maximum earthquake potential, considering regional and local geology and seismology and specific characteristics of local subsurface material. It is the earthquake that produces the maximum vibratory ground motion

37、for which safety-related structures, systems, and components (SSCs) are designed to perform their safety-related functions. safety class: Classification of SSCs based on their nuclear safety function. 3 System safety functions The function of the new fuel storage facility is to store and protect new

38、 fuel with or without control components at a plant. The safety functions of this facility are described in Sec. 3.1. 3.1 Functional requirements (1) Prevent criticality. This is accomplished by SSC design, configuration, and operational controls. (2) Prevent fuel damage. This is accomplished by SSC

39、 design, configuration, and operational controls. (3) Prevent theft or sabotage. This is accomplished by facility design and security controls. American National Standard ANSI/ANS-57.3-2018 3 3.2 Additional functional requirements for MOX fuel (1) Limit radiation exposure. This is accomplished by SS

40、C design, configuration, and operational controls. (2) Prevent unacceptable releases of radioactivity. This is accomplished by facility design, SSC design, configuration, and operational controls. 4 System definition 4.1 New fuel storage racks 4.1.1 Subsystem boundary The spatial envelope created by

41、 the new fuel storage racks includes cells and bracing, if provided. 4.1.2 Subsystem components This subsystem includes, but is not limited to, the following: (1) cells; (2) bracing (if provided); (3) walls and floor. 4.2 New fuel storage rack enclosure 4.2.1 Subsystem boundary The new fuel storage

42、rack enclosure includes protective envelope and security provisions. 4.2.2 Subsystem components This subsystem includes, but is not limited to, the following: (1) security enclosure; (2) fire protection; (3) radiation monitoring; (4) drain system; (5) embedments as required. 4.3 Receipt and inspecti

43、on equipment This subsystem includes, but is not limited to, the following: (1) inspection station; (2) inspection equipment; American National Standard ANSI/ANS-57.3-2018 4 (3) fuel handling equipment; (4) shipping container upending fixture. 5 Facility functional description 5.1 General The new fu

44、el storage facility functions to receive, inspect, handle, and store new fuel assemblies, control components, and fuel assemblies containing MOX fuel, as required. 5.2 Operational New fuel is received in the facility, inspected, and stored so that the fuel is protected from damage due to external ca

45、uses or sabotage and accidental criticality is precluded. The facility is designed to limit the release of radioactivity for all postulated accidents. 6 Design requirements The overall function of the new fuel storage facility is to provide for the safe and efficient receipt and storage of new fuel

46、assemblies with or without control components. The storage racks shall be designed and constructed to prevent criticality under normal and design-basis accident conditions. The facility shall be designed to ensure that storage and handling of fuel can be accomplished without damaging a fuel assembly

47、 or reducing the design margin to criticality. The facility shall be designed to meet security requirements. Provisions shall be made to install shielding as necessary to keep personnel exposure ALARA if MOX fuel is to be used in the plant. Provisions shall also be made for systems to detect and lim

48、it the release of radioactivity to the public and the exposure of operators as a result of a postulated accident. 6.1 Safety class, applicable codes, and standards The safety class for new fuel storage racks shall be designated per ANSI/ANS-58.14-2011 (R2017) 2. The design of the enclosure shall com

49、ply with the applicable parts of the following codes and standards and with the requirements given in Sec. 6.3 of this standard: (1) ACI 318-14, “Building Code Requirements for Reinforced Concrete” 3; (2) ACI 349-13, “Code Requirements for Nuclear Safety-Related Concrete Structures” 4; (3) ASCE/SEI 7-16, “Minimum Design Loads for Buildings and Other Structures” 5; (4) ANSI/ASME NQA-1-2015, “Quality Assurance Requirements for Nuclear Facility Applications” 6; (5) ANSI/AISC N690s1-15, “Specification for Safety-Related Steel Structures for Nuclear Facilities Including Supplement N