美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REGULATORY RESEARCH July 2014Revision 2

REGULATORY GUIDE

Technical Lead

Sarah Tabatabai

301-415-7000

REGULATORY GUIDE 1.60

DESIGN RESPONSE SPECTRA FOR

SEISMIC DESIGN OF NUCLEAR POWER PLANTS

A. INTRODUCTION

Purpose

This regulatory guide describes an approach that the staff of the U.S. Nuclear Regulatory

Commission (NRC) considers acceptable for defining response spectra for the seismic design of nuclear power plants to satisfy the requirements of Appendix A, “Seismic and Geologic Siting Criteria for Nuclear Power Plants,” to Part 100, “Reactor Site Criteria,” of Title 10 of the Code of Federal

Regulations (10 CFR Part 100) (Ref. 1). Regulatory Guide (RG) 1.60 forms part of the licensing basis for a number of nuclear power plants constructed during the 1970s and 1980s. Specifically, the safe shutdown earthquake ground motion (SSE) for these nuclear power plants is defined by a RG 1.60 response spectrum.

The prominent role of probabilistic seismic hazard assessments (PSHA) led to the establishment in 1997 of new requirements for the siting regulation in 10 CFR 100.23, “Geologic and Seismic Siting Criteria,” which specifies a different set of requirements to define the SSE. Regulatory Guide 1.208, “A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion” (Ref. 2) presents an NRC-acceptable approach to define the site-specific earthquake ground motion response spectrum (GMRS) that satisfies the requirements of 10 CFR 100.23and leads to the establishment of the SSE. The final SSE must also satisfy Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 3).

Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” of the Commission’s regulations (Ref. 4) provides a licensing framework for nuclear power plants. RG 1.60 has applicability within the 10 CFR Part 52 licensing framework. According to Section 5.3 of NRC Interim Staff Guidance (ISG) ISG-017, “Interim Staff Guidance on Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses,” (Ref. 5) a RG 1.60 response spectrum, anchored at 0.1 g, is considered to be an appropriately shaped response spectrum to define the minimum seismic input requirement at the foundation as required by Appendix S to 10 CFR Part 50. In addition, the certified Written suggestions regarding this guide or development of new guides may be submitted through the NRC’s public Web site under the Regulatory Guides document collection of the NRC Library at .

Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRC’s public Web site under the Regulatory Guides document collection of the NRC Library at . The regulatory guide is also available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at , under ADAMS Accession No. ML13210A432.

美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

seismic design response spectra (CSDRS) for several new reactor design certification applications1 are derived from RG 1.60 spectra with modified control points to broaden the spectra in the higher frequency range.

Applicable Regulations

? Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), “Domestic Licensing of Production and Utilization Facilities,” governs the licensing of domestic production and

utilization facilities.

? Appendix A, to 10 CFR Part 50, provides general design criteria (GDC) for nuclear power plants. The following GDC are of importance to the seismic design of nuclear power plants:

? GDC 1, “Quality Standards and Records,” requires, in part, that structures, systems, and components (SSCs) important to safety be designed, fabricated, erected, and tested to

quality standards commensurate with the importance of the safety functions to be

performed.

? GDC 2, “Design Bases for Protection Against Natural Phenomena,” requires that structures important to safety be designed to withstand the effects of expected natural

phenomena when combined with the effects of normal accident conditions without loss of

capability to perform their safety function

? Appendix S to 10 CFR Part 50, “Earthquake Engineering Criteria for Nuclear Power Plants,” provides the engineering criteria for nuclear power plants.

? 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” governs the issuance of early site permits, standard design certifications, combined licenses, standard design

approvals, and manufacturing licenses for nuclear power facilities

? 10 CFR Part 100, “Reactor Site Criteria,” requires NRC to consider the physical characteristics of a site including seismology and geology in determining the site’s acceptability for a nuclear

power reactor.

? 10 CFR 100.23, “Geologic and seismic siting criteria,” specifies the requirements to define the SSE.

? Appendix A to 10 CFR Part 100, “Seismic and Geologic Siting Criteria for Nuclear Power Plants,” provides the seismic and geologic siting criteria for nuclear power plants applicable to an

operating license applicant or holder whose construction permit was issued prior to January 10, 1997.

1 The NRC staff’s final safety evaluation reports for the AP1000, Economic Simplified Boiling-Water Reactor (ESBWR), and Advances Boiling-Water Reactor (ABWR) design certification applications are available under the respective ADAMS Accession Numbers ML112061231, ML110040021, and ML080670509. At the time of this RG update, the US-APWR design certification application is still under NRC review.

美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

Related Guidance

? Regulatory Guide (RG) 1.208, “A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion,” provides guidance on the development of the site-specific ground

motion response spectrum (GMRS). The GMRS represents the first part of the development of the Safe Shutdown Earthquake ground motion (SSE) for a site as a characterization of the

regional and local seismic hazard. The final SSE must satisfy both 10 CFR 100.23 and Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants,” to 10 CFR Part 50.

? Interim Staff Guidance (ISG-017), “Interim Staff Guidance on Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses,” supplements the

guidance provided to the staff in Sections 2.5 and 3.7 of NUREG-0800 and ISG-01, “Interim

Staff Guidance on Seismic Issues Associated with High Frequency Ground Motion in Design Certification and Combined License Applications” (Ref. 6).

? NUREG-0800, “Standard Review Plan (SRP) for the review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” (Ref. 7) Section 2.5.1 “Basic Geologic and Seismic

Information, Section 2.5.2 “Vibratory Ground Motion,” and Section 3.7.1 “Seismic Design

Parameters,” assures the quality and uniformity of staff safety reviews. It is also the intent of this plan to make information about regulatory matters widely available and to improve

communication between the NRC, interested members of the public, and the nuclear power

industry, thereby increasing understanding of the NRC’s review process.

Purpose of Regulatory Guides

The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agency’s regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.

Paperwork Reduction Act

This regulatory guide contains information collection requirements covered by 10 CFR Part 50, 10 CFR Part 52, and 10 CFR Part 100 that the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0011, 3150-0151 and 3150-0093, respectively. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.

美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

B. DISCUSSION

Reason for Change

The changes in this revision (Revision 2) reflect the applicability of RG 1.60 to the 10 CFR Part 52 licensing framework for new reactors. Other changes included updated reference materials, updated glossary, the text of the footnote on the first page, insertion of text in the Introduction explaining the purpose of regulatory guides, the Paperwork Reduction Act, update of the discussion in the

Implementation section, and inclusion of the accession numbers for the NRC’s Agencywide Documents Access and Management System (ADAMS) in the reference section.

Background

The NRC staff has used the 1973 version of RG 1.60 for numerous siting and licensing activities since its initial publication and it has also been used effectively by both domestic and international stakeholders. It forms part of the licensing basis for nuclear power plants constructed during the 1970s and 1980s. The new reactors, however, utilize other methods for determining the design response spectra through the calculation of the ground motion response spectra (GMRS) for early site permits (ESPs), or combined construction and operating licenses (COLs).

The prominent role of probabilistic seismic hazard assessments (PSHA) led to the establishment in 1997 of new requirements for the siting regulation in 10 CFR Part 100.23, “Geologic and Seismic Siting Criteria.” The new siting regulation, which applies to new reactors as well as nuclear power plant construction permits or operating licenses on or after January 10, 1997, requires, in part, the explicit

consideration of the uncertainties associated with geological and seismological characteristics through an appropriate analysis, such as PSHA. The role of PSHA also led to the development of RG 1.165 (Ref. 8), which was subsequently withdrawn and replaced by RG 1.208 in 2007. That guide provides general guidance on methods acceptable to the NRC staff for: (1) conducting geological, geophysical,

seismological, and geotechnical investigations; (2) identifying and characterizing seismic sources; (3) conducting a probabilistic seismic hazard assessment (PSHA); (4) determining seismic wave transmission (soil amplification) characteristics of soil and rock sites; and (5) determining a site-specific, performance-based GMRS, satisfying the requirements of paragraphs (c), (d)(1), and (d)(2) of 10 CFR 100.23, and leading to the establishment of a Safe Shutdown Earthquake (SSE) to satisfy the design requirements of Appendix S to 10 CFR Part 50. According to Appendix S to 10 CFR Part 50, the foundation level ground motion must be represented by an appropriate response spectrum with a peak ground acceleration of at least 0.1 g. The steps necessary to develop the final SSE are described in Chapter 3, “Design of

Structures, Components, Equipment and Systems,” of NUREG-0800, and Regulatory Position 5.4 of RG

1.208 provides a detailed description of the development of the final SSE. ISG-017 supplements the

guidance provided in NUREG-0800 and states that RG 1.60, anchored at 0.1 g, is an appropriately shaped response spectrum to define the minimum seismic input requirement at the foundation as required by Appendix S to 10 CFR Part 50.

Although RG 1.60 is no longer used to characterize the hazard for the seismic design of nuclear power plants, the CSDRS for several new reactor designs are derived from RG 1.60 spectra with modified control points to broaden the spectra in the higher frequency range. Specifically, RG 1.60 spectral values are based on deterministic values for western United States earthquakes, however, recent observations have shown that high frequency motions at central and eastern United States (CEUS) rock sites may be significantly greater than motions recorded at WUS rock sites.

美国核管会2014版RG1.60 (NRC-RG1.60-2014版)

Response Spectra Shapes

Appendix A to 10 CFR Part 100, which now applies only to an operating license applicant or

holder whose construction permit was issued prior to January 10, 1997, specifies a number of required investigations for determining the SSE, that is, the potential maximum earthquake for which structures, systems, and components important to safety, are designed to sustain and remain functional.

The recorded ground accelerations and response spectra of past earthquakes provide a basis for the design of structures to resist earthquakes. Appendix A requires developing response spectra corresponding to the expected maximum ground acceleration for a site, but does not give a specific method for defining the response spectra. The response spectra developed for a site are known as the Design Response Spectra. The Design Response Spectra can be developed statistically from response spectra of past strong-motion earthquakes, as was done by Newmark, Blume and Kapur (Ref. 9, 10, 11 and 12). After reviewing these documents, the Atomic Energy Commission (AEC) (now NRC) staff determined that this procedure for defining the Design Response Spectra on sites underlain by either rock or soil deposits and covering all frequencies of interest was acceptable. However, for unusually soft sites, modification to this procedure will be required.

The horizontal and vertical component Design Response Spectra in Figures 1 and 2, respectively, of this guide correspond to a maximum horizontal ground acceleration of 1.0 g. For sites with different acceleration values specified for the design earthquake, the Design Response Spectra should be linearly scaled from Figures 1 and 2 in proportion to the specified maximum horizontal ground acceleration. For sites that (1) are relatively close to the epicenter of an expected earthquake or (2) have physical

characteristics that could significantly affect the spectral pattern of input motion, such as being underlain by poor soil deposits, the procedure described above will not apply. In these cases, the Design Response Spectra should be developed individually according to the site characteristics.

1. The Horizontal Component - The numerical values of design displacements, velocities, and

accelerations for the horizontal component Design Response Spectra are obtained by multiplying the corresponding values of the maximum ground displacement and acceleration by the factors given in Table 1 of this guide. In this procedure, the configurations of the horizontal component Design Response Spectra for each of the two mutually perpendicular horizontal axes are shown in Figure 1 of this guide. These shapes agree with those developed by Newmark, Blume, and Kapur and shown in Figure 15 of Ref. 9 as well as Figure 9 of Ref. 10. In Figure 1, the base diagram consists of three parts: the bottom line on the left part represents the maximum ground

displacement, the bottom line on the right part represents the maximum acceleration, and the

middle part depends on the maximum velocity. The horizontal component Design Response

Spectra in Figure 1 of this guide correspond to a maximum horizontal ground acceleration of 1.0 g. The maximum ground displacement is taken proportional to the maximum ground

acceleration, and is set at 36 inches for a ground acceleration of 1.0 g. The displacement region lines of the Design Response Spectra are parallel to the maximum ground displacement line and are shown on the left of Figure 1. The velocity region lines slope downward from a frequency of 0.25 cycles per second (cps) or Hertz (Hz) (control point D) to a frequency of 2.5 cps (control point C) and are shown at the top. The remaining two sets of lines between the frequencies of 2.5 cps and 33 cps (control point A), with a break at a frequency of 9 cps (control point B), constitute the acceleration region of the horizontal Design Response Spectra. For frequencies higher than 33 cps, the maximum ground acceleration line represents the Design Response Spectra.