ANS 2.2-2016 Earthquake Instrumentation Criteria for Nuclear Power Plants.pdf

1、An American National StandardPublished by the American Nuclear Society 555 N. Kensington AveLa Grange Park, IL 60526ANSI/ANS-2.2-2016Earthquake Instrumentation Criteria for Nuclear Power PlantsANSI/ANS-2.2-2016ANSI/ANS-2.2-2016 American National Standard Earthquake Instrumentation Criteria for Nucle

2、ar Power Plants Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-2.2 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Approved July 14, 2016 by the American National Standards I

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18、ican National Standard ANSI/ANS-2.2-2016 American National Standard ANSI/ANS-2.2-2016 i Foreword (This foreword is not a part of American National Standard “Earthquake InstrumentationCriteria for Nuclear Power Plants,” ANSI/ANS-2.2-2016.) The purpose of this standard is to specify for water-cooled n

19、uclear power plants the minimum requirements for earthquake instrumentation. Should an earthquake occur, the instrumentation provides information on the vibratory ground motion and resultant vibratory responses of representative Category I structures (defined in U.S. Nuclear Regulatory Commission Re

20、gulatory Guide 1.29, “Seismic Design Classification for Nuclear Power Plants”) so that an evaluation can be made as to (1) whether or not the design response spectra have been exceeded; (2) whether or not the motion was damaging through determination of its standardized cumulative absolute velocity

21、(CAV) as incorporated in ANSI/ANS-2.23-2016, “Nuclear Power Plant Response to an Earthquake”; (3) whether or not the calculated vibratory responses used in the design of the representative Category I structures and equipment have been exceeded at instrumented locations; (4) the degree of applicabili

22、ty of the mathematical models used in the seismic analysis of the building and equipment. In addition, instrumentation could be provided to furnish specific information that would increase knowledge and understanding of seismic design. The problem of determining what additional instrumentation is ne

23、eded to perform this function should be the basis of research and development programs and is not addressed in this standard. The seismic design of nuclear power facilities requires, in part, (1) the determination of (a) site-specific earthquake ground motion response spectra, and (b) site-independe

24、nt certified broadband smooth response spectra, referred to as certified seismic design response spectra (CSDRS); (2) the construction of mathematical models for dynamic analysis from which the vibratory response of structures and equipment to the input vibratory ground motion can be calculated. Sei

25、smic designs for nuclear power plants utilize advanced analytical and design techniques. Therefore, evidence that the earthquake ground motion response spectra, developed from actual instrumental measurements, did not exceed the design basis spectral values, or that the CAV from the free-field instr

26、ument showed that the motion was not damaging, in accordance with ANSI/ANS-2.23-2016, “Nuclear Power Plant Response to an Earthquake,” would give reasonable assurance that plant structures and equipment were not damaged or made inoperable. In addition, the determination by actual instrument data of

27、(a) the resultant vibratory responses of representative structures, (b) the input to supported equipment, and (c) the check of the applicability of mathematical models used in the dynamic analysis would give further assurance that plant structures or equipment was not damaged. When an earthquake occ

28、urs, it is important to determine as soon as possible (within 4 hours) whether or not the free-field motion exceeded predetermined conditions in accordance with ANSI/ANS-2.23-2016. An acceptable instrumentation system would provide necessary data in a conveniently usable form for making this determi

29、nation in a timely manner. Through the use of commercially available instruments, and by specifying their functional and operational requirements, an acceptable instrumentation system can be assembled, procured, installed, and operated. This standard provides the minimum requirements for an acceptab

30、le seismic instrumentation system. American National Standard ANSI/ANS-2.2-2016 ii The basic and most important instrument for measuring vibratory motion is the data acquisition unit (DAU), a subsystem of the seismic monitoring system (time-history accelerograph in previous versions of this standard

31、), that acquires, stores, and transmits digital data from one or more sensors. A DAU consists of amplifiers, analog-to-digital converter, storage, telemetry, and timing source (for instance, global positioning system or network time protocol). From the resulting time-history records, the peak accele

32、rations and duration can be determined, and the response spectra and CAV can be derived by computation. This standard references documents and other standards that may have been, or become, superseded or withdrawn at the time the standard is applied. A statement has been included in the reference se

33、ction that provides guidance on the use of such references. This standard does not explicitly incorporate the concepts of generating risk-informed insights, performance-based requirements, or a graded approach to quality assurance. The user is advised that one or more of these techniques could enhan

34、ce the application of this standard. This standard was prepared by Working Group ANS-2.2 of the American Nuclear Society Standards Committee. This is a major revision to the ANSI/ANS-2.2-2002 standard. All comments received were reviewed and, where possible, were incorporated. Working Group ANS-2.2

35、had the following membership during its work on this standard: F. Ostadan (Chair), Bechtel Corporation J. Ake, U.S. Nuclear Regulatory Commission M. Ciudad-Real, Kinemetrics, Inc. V. Graizer, U.S. Nuclear Regulatory Commission R. J. Hunt, Consolidated Nuclear Security LLC J. J. Johnson, James J. Joh

36、nson and Associates R. M. Kenneally, Individual R. Lee, Los Alamos National Laboratory M. Lewis, Bechtel Corporation J. Marrone, Bechtel Corporation R. Nigbor, University of California, Los Angeles This standard was prepared under the guidance of the Siting: Seismic Subcommittee, which had the follo

37、wing membership at the time of its approval: Q. Hossain (Chair), Lawrence Livermore National Laboratory J. Xu (Vice Chair), U.S. Nuclear Regulatory Commission E. Gibson, Defense Nuclear Facilities Safety Board K. Hanson, Individual R. Kassawara, Electric Power Research Institute F. Ostadan, Bechtel

38、Corporation J. Savy, Individual I. Wong, URS Professional Solutions LLC (an AECOM Company) The Environmental and Siting Consensus Committee (ESCC) had the following membership at the time of its approval of this standard: C. A. Mazzola (Chair), CB (2) procedures for evaluating records obtained from

39、seismic instrumentation and instructions for the treatment of data. These procedures and instructions are specified in ANSI/ANS-2.23-2016 11); (3) instrumentation for nuclear power plant designs incorporating base isolation techniques. 2 Purpose This standard defines the minimum requirements for an

40、earthquake instrumentation system to be installed at nuclear power plants. These instruments are intended to provide timely (within 4 hours) information on the earthquake ground motion at the site and the corresponding response vibratory motion of Seismic Category I structures, when subjected to ear

41、thquake ground motion. By comparing this information with the vibratory motions used in the facilitys seismic design,2)an evaluation can be made as to whether or not the design basis vibratory motions have been exceeded. 3 Acronyms and definitions 3.1 Shall, should, and may shall, should, and may: T

42、he 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. 3.2 List of acronyms ADC: analog-to-digital converter ALARA: as low as reasonably achievable CSDRS: cert

43、ified seismic design response spectra CAV: cumulative absolute velocity 1)Numbers in brackets refer to corresponding numbers in Sec. 10, “References.” 2)Appendix A provides an overview of applicable licensing practices used in the issuance of early site permits and combined licenses. American Nation

44、al Standard ANSI/ANS-2.2-2016 2 COL: combined license DAU: data acquisition unit DCD: design control document DCPP: Diablo Canyon Power Plant ESP: early site permit FIRS: foundation input response spectra GMRS: ground motion response spectra GPS: global positioning system NRC: U.S. Nuclear Regulator

45、y Commission NTP: network time protocol OBE: operating basis earthquake OSHA: Occupational Safety and Health Administration PGA: peak ground acceleration PGV: peak ground velocity PGD: peak ground displacement SMS: seismic monitoring system SOH: state of health SSCs: structures, systems, and compone

46、nts SSE: safe shutdown earthquake ground motion SSI: soil-structure interaction S/T: seismic trigger 3.3 Definitions acceleration sensor: An instrument capable of sensing absolute acceleration and producing an analog or digital signal that can be transmitted to a recorder. Other sensor types, for ex

47、ample, velocity or displacement, are not included in this standard. accessible instruments: Instruments or sensors whose locations permit ready access during plant operation without violation of applicable safety regulations, such as those of the Occupational Safety and Health Administration (OSHA),

48、 or regulations that address plant security or radiation protection safety. certified standard design: See “standard design certification.” channel calibration (primary calibration): The determination and, if required, adjustment of an instrument, sensor, or system such that it responds within a spe

49、cified range to an acceleration, velocity, or displacement input, as applicable, or responds as intended to the stimulus provided by a known input. American National Standard ANSI/ANS-2.2-2016 3 channel check: The qualitative verification of the functional status of the time-history acceleration sensor. This check is an “in situ” test and may be the same as a channel functional test. channel functional test (secondary calibration): The determination, without adjustment, that an instrument, sensor, or system responds to a known input of such character that it will verify that the instru