ANSI ANS 2.30-2015 Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities.pdf

《ANSI ANS 2.30-2015 Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities.pdf》由会员分享，可在线阅读，更多相关《ANSI ANS 2.30-2015 Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities.pdf（59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-2.30-2015Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear FacilitiesANSI/ANS-2.30-2015ANSI/ANS-2.30-2015 American National Standard Criteria fo

2、r Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-2.30 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 605

3、26 USA Approved May 26, 2015 by the American National Standards Institute, Inc. American National Standard ANSI/ANS-2.30-2015 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 app

4、roval procedure 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,

5、 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 industry, consumers, gove

6、rnmental 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 the standard. By publicat

7、ion 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, occurring through develo

8、pments 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 copies in their posses

9、sion 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. Responses to inquiries about requirements, recommendations, and/or permissive statements

10、(i.e., “shall,” “should,” and “may,” respectively) 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

11、Society Headquarters. Published by American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA This document is copyright protected. Copyright 2015 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-2.30-2015 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-2.30-2015 Inquiry Requests Inquiry Format The American Nuclear Society (ANS) Standards Committee will provide responses to inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and/or “may,” respectively) in American National Standards

14、that are developed 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 req

15、uirements in a standard 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 Web si

16、te or by contacting the ANS Scientific Publications and Standards Department. Inquiry requests must 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

17、/or table; (3) the purposes 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 ATTN: Scientific Publications and Standards Department 555 N. Kensington Aven

18、ue La Grange Park, IL 60526 or standardsans.org American National Standard ANSI/ANS-2.30-2015 American National Standard ANSI/ANS-2.30-2015 i Foreword (This foreword is not a part of the American National Standard “Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Faci

19、lities,” ANSI/ANS-2.30-2015.) This standard provides criteria and guidelines for assessing permanent ground deformation (PGD) hazard due to tectonic surface fault rupture and deformation at nuclear facilities. Specifically, the purpose of this standard is to provide an outline of procedures and meth

20、ods for performing probabilistic fault displacement hazard analysis (PFDHA) and probabilistic tectonic deformation hazard analysis (PTDHA). This standard replaces ANSI/ANS-2.7-1982, “Criteria and Guidelines for Assessing Capability for Surface Faulting at Nuclear Power Plants,” which is obsolete bec

21、ause of changes in the state-of-knowledge, technical methods, public concerns, and regulatory programs. This new standard includes updated information to make it useful for siting/licensing nuclear facilities in the U.S. This standard is one of a series of national standards designed to provide crit

22、eria and guidelines to promote uniform and effective assessment of seismic hazards at nuclear facilities. These hazards must be properly identified and characterized commensurate with the level of risk and design-requirements associated with each nuclear facility as specified in ANSI/ANS-2.26-2004 (

23、R2010), “Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design.” Two complementary standards describe procedures for performing site characterization and assessing seismic hazards, respectively: ANSI/ANS-2.27-2008, “Criteria for Investigations of Nuclear Facility

24、Sites for Seismic Hazard Assessments,” and ANSI/ANS-2.29-2008, “Probabilistic Seismic Hazard Analysis.” 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

25、 provides guidance on the use of references. The ANS-2.30 Working Group of the Standards Committee of the American Nuclear Society (ANS) had the following membership: I. Wong (Chair), URS Corporation W. Bryant, California Geological Survey R. Chen, California Geological Survey K. Kelson, URS Corpora

26、tion (now at U.S. Army Corps of Engineers) J. Kimball, Defense Nuclear Facility Safety Board (now at Rizzo Associates) J. Litehiser, Bechtel Corporation S. Olig, URS Corporation D. Schwartz, U.S. Geological Survey A. Stieve, U.S. Nuclear Regulatory Commission D. Wells, AMEC Environment thus, criteri

27、a and guidelines have not been defined previously. PGD due to fault rupture is a potential hazard for nuclear facilities founded across or near a fault. In this standard, only coseismic PGD hazard related to movement on crustal faults is addressed. Deformation in the form of creep or afterslip and u

28、plift and subsidence during subduction zone earthquakes is not addressed. Non-tectonic deformation, as described in Section 5.1, is not addressed in this standard. Methods to investigate and characterize surface fault displacement and tectonic deformation hazards have advanced significantly, justify

29、ing a new standard. Specifically, it is possible to quantify the expected PGD from surface or near-surface fault rupture due to advances in geologic, geomorphic, and paleoseismic techniques used to identify and quantify the location, rate, and amount of Quaternary deformation as well as empirical ob

30、servations of PGD resulting from historical earthquakes. Modern engineering practice has developed sufficiently such that the design or retrofit of structures, systems, or components (SSCs) might be able to accommodate or resist certain amounts of earthquake-induced surface rupture or other types of

31、 ground deformation. Therefore, characterization of PGD is a critical step during the siting and design of engineered facilities that are to be located in areas where such deformation may occur. This standard replaces ANSI/ANS-2.7-1982 (withdrawn), “Criteria and Guidelines for Assessing Capability f

32、or Surface Faulting at Nuclear Power Plant Sites,” 11which is obsolete because of changes in technical methods, public concerns, and regulatory programs. This new standard includes updated information to make it useful for siting/licensing nuclear facilities in the U.S. This standard does not specif

33、y methods for estimating the probability of other seismically induced hazards such as soil liquefaction, soil settlement, landsliding, and earthquake-induced flooding. These hazards may be applicable for certain sites and need to be evaluated and included in design requirements. This standard is one

34、 of a series of national standards designed to provide criteria and guidelines to promote uniform and effective assessment of seismic hazards at nuclear facilities. These hazards must be properly identified and characterized commensurate with the level of risk and design 1Numbers in brackets refer t

35、o corresponding numbers in Sec. 11, “References.” American National Standard ANSI/ANS-2.30-2015 2 requirements associated with each nuclear facility, as specified in ANSI/ANS-2.26-2004 (R2010), “Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design” 2. As defined

36、in ANSI/ANS-2.26-2004 (R2010) 2, a nuclear facility is a facility that stores, processes, tests, or fabricates radioactive materials in such form and quantity that a significant nuclear hazard to the workers, to the off-site public, or to the environment may exist. These include, but are not limited

37、 to, commercial nuclear power plants, nuclear fuel manufacturing facilities, nuclear material waste processing, storage, fabrication, and reprocessing facilities, uranium enrichment facilities, tritium production and handling facilities, and radioactive materials laboratories. Additional criteria ma

38、y be specified by an applicable regulatory authority such as the U.S. Nuclear Regulatory Commission (NRC). The guidelines and requirements provided in this standard are applicable for the design and evaluation of Seismic Design Category (SDC)-3, SDC-4, and SDC-5 facilities. These can also be applied

39、 to SDC-1 and SDC-2 or other non-U.S. Department of Energy (DOE) facilities, if, for safety, economic, or other reasons, a site-specific seismic hazard evaluation is necessary. Two complementary standards describe procedures for performing site characterization and assessing seismic hazards: ANSI/AN

40、S-2.27-2008, “Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments,” 3 and ANSI/ANS-2.29-2008, “Probabilistic Seismic Hazard Analysis” 4. ANSI/ANS-2.27-2008 3 provides criteria and guidelines for conducting geological, seismological, and geotechnical investigations ne

41、eded to provide information to support the following: (1) seismic source characterization input to a probabilistic seismic hazard analysis (PSHA); (2) evaluation of surface fault rupture hazard; (3) site response analysis; and (4) evaluation of seismic-induced ground failure hazard. ANSI/ANS-2.29-20

42、08 4 outlines standard criteria and procedures to perform a PSHA for earthquake ground shaking hazard at nuclear facilities. Appropriate criteria and guidelines are outlined herein to ensure that the current state-of-the-art methodology is being used for completing either PFDHA or PTDHA. The selecti

43、on of specific techniques and level of detail required to assess seismic-induced hazards are dependent on both the nature of the nuclear facility (i.e., SDC), as defined by ANSI/ANS-2.26-2004 (R2010) 2, and site-specific conditions. Execution of this standard requires two prior conditions: (1) defin

44、ing the seismic design category for the facility; and (2) executing a site characterization program following the requirements and guidelines given in ANSI/ANS-2.27-2008 3 and in Section 5 of this standard. 2 Definitions and acronyms 2.1 Shall, should, and may shall, should, and may: The word “shall

45、” is used to denote a requirement; the word “should” is used to denote a recommendation; and the word “may” is used to denote a permission, neither a requirement nor a recommendation. 2.2 Definitions aleatory uncertainty: The uncertainty inherent in a nondeterministic (i.e., stochastic, random) phen

46、omenon. Aleatory uncertainty, sometimes referred to as “aleatory variability,” is accounted for by modeling the phenomenon in terms of a probability model. In principle, aleatory uncertainty American National Standard ANSI/ANS-2.30-2015 3 cannot be reduced by the accumulation of more data or additio

47、nal information, but the detailed characteristics of the probability model can be improved. Sometimes aleatory uncertainty is called “randomness.” blind fault: A buried fault or fault zone that does not rupture to the ground surface but can cause surface deformation. coseismic deformation: Movement

48、of the ground surface due to fault displacement during an earthquake. epistemic uncertainty: Uncertainty attributable to incomplete knowledge about a phenomenon that affects the ability to model it. Epistemic uncertainty is captured by considering a range of model parameters within a given expert in

49、terpretation or multiple expert interpretations, each of which is assigned an associated weight representing statistical confidence in the alternatives. In principle, epistemic uncertainty can be reduced by the accumulation of additional information associated with the phenomenon. The uncertainty in the parameters of the probability distribution of a physical phenomenon is epistemic. fault/fault zone: A fracture in the earth along which blocks on either side have moved with respect to one another. Faulting may occur along multiple planes (see Fault Displacement) and inclu