ANS 58.16-2014 Safety Categorization and Design Criteria for Nonreactor Nuclear Facilities.pdf

1、 ANSI/ANS-58.16-2014American National Standard Safety Categorization and Design Criteria for Nonreactor Nuclear FacilitiesSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-58.16Published by theAmerican Nuclear Society555 North Kensington A

2、venueLa Grange Park, Illinois 60525 USAApproved September 9, 2014by theAmerican National Standards Institute, Inc.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 and that a consensus of

3、 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 meeting the criteria for Ameri

4、can 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 agencies, and general interest g

5、roups. 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 standard, the American Nuclear

6、 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 state of the art, may be con

7、sidered 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 It may be reaffirmed, revised, or withdrawn at any time in accordance with established procedures.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 establish that they are of the

8、 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. Responses to inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and “may,” respec

9、tively) should be sent to the 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 Society Headquarters.Published byAmerican Nu

10、clear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAThis document is copyright protected.Copyright 2014 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines, should read “Extracted from American National Standard ANSI/ANS-58.16-

11、2014 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 AmericaAmerican National StandardAmerican National Standard ANSI/ANS-58.16-201

12、4The 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 and approved by ANS. Responses to inquiri

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14、sign, 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 Web site or by contacting the ANS standards administrator.Inquiry

15、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 table;(3) the purposes of the inquiry; (4) the inquiry stated in a clear, concise

16、manner; (5) a proposed reply, if the inquirer is in a position to offer one.Inquiries should be addressed to: American Nuclear SocietyATTN: Standards Administrator 555 N. Kensington AvenueLa Grange Park, IL 60526or standardsans.orgInquiry RequestsInquiry FormatAmerican National Standard ANSI/ANS-58.

17、16-2014American National Standard ANSI/ANS-58.16-2014-i-(This foreword is not a part of American National Standard “Safety Categorization and Design Criteria for Nonreactor Nuclear Facilities,” ANSI/ANS-58.16-2014.)Nonreactor nuclear facilities are designed, constructed, and operated using regulatio

18、ns, standards, and practices to assure that the workers in the facilities and members of the public outside the facilities are safe during the normal operations of the facilities and also in case of abnormal events or accidents. This is achieved through judicious categorization of structures, system

19、s, and components (SSCs) and specific administrative controls (SACs) to prevent or mitigate such events. The categorization determines the types and levels of controls needed, based on the hazards at the facilities. This standard provides a roadmap to identifying existing industry codes and standard

20、s for reliable design, construction, and operation of various categories of controls, and also some new requirements that are not addressed in existing standards. This standard provides criteria for the categorization of SSCs and SACs specifically for nonreactor nuclear facilities. Standards for des

21、ign of categories of hazard controls are also identified. It has an overall objective similar to American National Standards Institute (ANSI)/American Nuclear Society (ANS) American National Standard ANSI/ANS-58.14-2011, “Safety and Pressure Integrity Classification Criteria for Light Water Reactors

22、,” in that both provide safety categorization criteria and design codes and standards for design. While the objectives of these two standards are the same (i.e., specification of appropriate design codes and standards for safety features), ANSI/ANS-58.16-2014 requires the determination of design-bas

23、is events (DBEs) as a first step, which is not required as part of the procedures invoked by ANSI/ANS-58.14-2011 for reasons discussed below.Nonreactor nuclear facilities are often unique and of a one-of-a-kind design. Operators of these facilities can work very close to the hazards themselves. The

24、hazards associated with nonreactor nuclear facilities are highly dependent on the nature of the facility and its mission. For example, those hazards can involve exposure to radioactive and other hazardous materials as a result of fires, explosions, process upsets, spills and leaks, as well as inadve

25、rtent nuclear criticality. A hazard analysis is required to identify the hazards and the type of events that can be associated with them. These analyses are used to develop DBEs and the needed safety functions to prevent or mitigate them to protect workers and the public.Light water reactors are les

26、s diverse, and DBEs are based on experience with licensing safety reviews over a period of decades, focused on protection of the public. Facility workers are not in immediate contact with the hazardous materials. The very high energy associated with nuclear fission and the high level of fission prod

27、ucts contained in a reactor core and their energy of decay lead to a focus on ensuring reactor core cooling, including pressure boundary integrity. A new hazard analysis is not usually needed because DBEs have been preselected.As a result, readers, reviewers, and users of this standard should not ex

28、pect that there would be a high degree of correlation between this standard and ANSI/ANS-58.14-2011.This standard might reference documents and other standards that have been superseded or withdrawn at the time the standard is applied. A statement has been included in the references section that pro

29、vides guidance on the use of references. This standard does not incorporate the concepts of generating risk-informed insights or performance-based requirements. The user is advised that one or more of these techniques could enhance the application of this standard.ForewordAmerican National Standard

30、ANSI/ANS-58.16-2014-ii-The ANS-58.16 Working Group acknowledges the significant contributions made to this standard by Dr. Richard W. Englehart and Dr. John D. Stevenson who passed away before the standard was issued. Both Dr. Englehart and Dr. Stevenson played key roles in all phases of the standar

31、d, starting with the formulation, through the development process, and preparation of the final draft. The ANS-58.16 Working Group of the Standards Committee of the American Nuclear Society had the following membership at the time the standard was developed: P. K. Guha (Chair), U.S. Department of En

32、ergyR. G. Eble (Vice Chair), Savannah River Site, MOX ProjectR. Bunt, Southern Nuclear Operating Company C. Chaves, U.S. Department of EnergyD. H. Cook, Oak Ridge National LaboratoryG. Couture, Westinghouse Electric Company, LLCM. Dayani, Savannah River Site, MOX ProjectR. W. Englehart, IndividualG.

33、 L. Jones, U.S. Department of Energy, Office of River ProtectionP. K. Niyogi, U.S. Department of EnergyK. M. Ramsey, U.S. Nuclear Regulatory CommissionM. L. Ramsay, U. S. Department of Energy, RichlandL. Restrepo, Nuclear Safety AssociatesS. K. Sen, U.S. Department of EnergyJ. D. Stevenson, Individu

34、alThe ANS-22 Subcommittee, System Design Criteria, had the following membership at the time of its approval of this standard:R. M. Ruby, (Chair), Constellation EnergyD. G. Newton, (Vice Chair), AREVA Inc.N. Brown, IndividualP. K. Guha, U.S. Department of EnergyE. M. Johnson, IndividualL. E. Kreider,

35、 Engineering Planning shall, should, and may; and definitions 22.1. List of acronyms 22.2. Shall, should, and may 32.3. Definitions . 33 General requirements 53.1. Regulatory basis 53.2. Methodology . 53.3. Hazard analysis . 63.4. Determination of DBEs 63.5. Unmitigated consequence analysis 63.6. Se

36、lection, categorization, and design of hazard controls 64 Safety categorization criteria . 74.1. Categorization criteria 75 Design criteria 85.1. General design criteria 85.1.1 Single-failure criterion 85.1.2 Environmental qualification . 85.1.3 Support systems 85.1.4 Interface design . 95.1.5 Impai

37、rment of safety functions. 95.1.6 Criticality hazard control 95.2. Civil-structural 95.3. Mechanical . 95.3.1 Process system equipment 105.3.2 Ventilation . 105.3.3 Mechanical handling equipment 115.3.4 Fire safety equipment . 115.3.5 Explosion safety equipment 115.4. Electrical, instrumentation, an

38、d controls 125.5. Quality assurance 125.6. Specific administrative controls . 126 References . 14AppendicesAppendix A General Relationship Between ANSI/ANS-58.16-2014 Safety Categorization and Current NRC-DOE Safety Categorizations for Other Than Reactor Facilities. 19Appendix B Safety Categorizatio

39、n Process 22Appendix C Structures, Systems, and Components Boundary Criteria 31Appendix D References by Organizations and Bibliography 35FiguresFigure B.1 Safety categorization process flow diagram . 24Figure C.1 Boundary criteria for SC-2 and SC-3 process systems 33-v-American National Standard ANS

40、I/ANS-58.16-2014Figure C.2 Boundary criteria for SC-2 or SC-3 process lines penetrating confinement . 33Figure C.3 Boundary criteria SC-1, SC-2, and SC-3 instrument lines . 34TablesTable 1 General safety criteria for safety categorization of controls . 7Table 2 Codes and standards for SC-2 and SC-3

41、process equipment 10Table 3 Codes and standards for SC-2 and SC-3 ventilation system components 11Table 4 Codes and standards for SC-2 and SC-3 mechanical handling equipment 11Table 5 Codes and standards for SC-2 and SC-3 safety categories . 13Table A.1 Typical correlation of ANSI/ANS-58.16-2014 saf

42、ety categories with existing DOE and NRC safety categorization of SSCs . 20Table A.2 Guidance of safety criteria for safety categorization of controls 201American National Standard ANSI/ANS-58.16-2014vi1American National Standard ANSI/ANS-58.16-20141 IntroductionThis American National Standard Insti

43、tute (ANSI)/American Nuclear Society (ANS) Amer-ican National Standard ANSI/ANS-58.16-2014 provides criteria for the categorization of struc-tures, systems, and components (SSCs) and spe-cific administrative controls (SACs) as hazard controls, for nonreactor nuclear facilities. Stan-dards for the de

44、sign of hazard controls are iden-tified based on a safety category (SC).The criteria for categorization of hazard con-trols as safety SSCs and SACs are largely de-terministic and are based on the magnitude of consequences of a set of unmitigated postulated design-basis events (DBEs). Consequences ar

45、e in terms of radiological dose levels and hazard-ous chemical exposure levels to workers and the public. In this standard, the categories are denoted by SC-1, SC-2, and SC-3, with SC-3 being the high-est category with the most stringent design re-quirements.Throughout, this standard makes reference

46、 to various standards and regulations. Those ref-erences are denoted by brackets. A list of those bracketed references is provided in Sec. 6. 1.1 ScopeThis standard specifies criteria for categoriza-tion of SSCs and SACs that have a safety func-tion based on radiological and/or chemical dose and exp

47、osure levels for the public and workers. The safety categorization leads to codes and standards that are needed for reliable design, construction, and operations commensurate with the safety categorization.The safety categorization criteria specified in this standard will(1) establish an objective a

48、nd technically based rationale for the determination of safety cat-egorization;(2) ensure that all hazard controls required by the safety design basis are appropriately categorized;(3) establish a basis for consistency (i.e., mini-mize categorization differences among simi-lar items in a facility).

49、1.2 PurposeThe purpose of this standard is the following: (1) Specify criteria for categorization of safety SSCs; (2) Select industry codes and standards for re-liable design, construction, and operations commensurate with the safety categoriza-tion.To meet these objectives, the standard specifies the requirements in the following steps:(1) identification of hazards;(2) evaluation of hazards;(3) selection of DBEs;(4) unmitigated accident analysis of DBEs;(5) identification of safety