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NUREG 1 60 Seismic | Nuclear Regulatory Commission | Spectral Density
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REGULATORY GUIDE 1.60
DESIGN RESPONSE SPECTRA FOR
SEISMIC DESIGN OF NUCLEAR POWER PLANTS
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
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 http://www.nrc.gov/reading-rm/doc-collections/regguides/contactus.html.
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 http://www.nrc.gov/readingrm/doc-collections/. The regulatory guide is also available through the NRC’s Agencywide Documents Access and Management
System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML13210A432.
• Appendix A to 10 CFR Part 100. “Earthquake Engineering Criteria for Nuclear Power Plants. that structures.23. and ML080670509. • 10 CFR Part 52.” governs the issuance of early site permits. “Domestic Licensing of Production and Utilization Facilities. • Appendix A.” provides the engineering criteria for nuclear power plants.” requires. erected. and tested to quality standards commensurate with the importance of the safety functions to be performed. and components (SSCs) important to safety be designed. ML110040021.” governs the licensing of domestic production and utilization facilities.60 spectra with modified control points to broaden the spectra in the higher frequency range. “Quality Standards and Records.” 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. • GDC 2. provides general design criteria (GDC) for nuclear power plants. Certifications. Applicable Regulations • Title 10. • 10 CFR 100. “Seismic and Geologic Siting Criteria for Nuclear Power Plants. and Advances Boiling-Water Reactor (ABWR) design certification applications are available under the respective ADAMS Accession Numbers ML112061231. combined licenses. “Licenses. to 10 CFR Part 50. systems.” 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. The following GDC are of importance to the seismic design of nuclear power plants: • GDC 1. 1 The NRC staff’s final safety evaluation reports for the AP1000. Part 50. in part. Economic Simplified Boiling-Water Reactor (ESBWR).” specifies the requirements to define the SSE. standard design certifications. standard design approvals. fabricated. and manufacturing licenses for nuclear power facilities • 10 CFR Part 100. . “Reactor Site Criteria. the US-APWR design certification application is still under NRC review. and Approvals for Nuclear Power Plants. “Geologic and seismic siting criteria. 1997. “Design Bases for Protection Against Natural Phenomena. of the Code of Federal Regulations (10 CFR Part 50). At the time of this RG update.” 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.seismic design response spectra (CSDRS) for several new reactor design certification applications1 are derived from RG 1.
2 “Vibratory Ground Motion.” to 10 CFR Part 50.23 and Appendix S. 6). and to provide guidance to applicants. respectively. “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). 3150-0151 and 3150-0093. thereby increasing understanding of the NRC’s review process.208.” (Ref. • Interim Staff Guidance (ISG-017).” supplements the guidance provided to the staff in Sections 2. 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.5 and 3.7. “Interim Staff Guidance on Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses. and the nuclear power industry. interested members of the public. Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 50. The final SSE must satisfy both 10 CFR 100.” assures the quality and uniformity of staff safety reviews. “Standard Review Plan (SRP) for the review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition. and 10 CFR Part 100 that the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0011.1 “Basic Geologic and Seismic Information.1 “Seismic Design Parameters.5.5.Related Guidance • Regulatory Guide (RG) 1. Regulatory guides are not substitutes for regulations and compliance with them is not required. and a person is not required to respond to. .7 of NUREG-0800 and ISG-01. 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. • NUREG-0800. 7) Section 2. an information collection request or requirement unless the requesting document displays a currently valid OMB control number. to explain techniques that the staff uses in evaluating specific problems or postulated accidents.” and Section 3. 10 CFR Part 52. “Earthquake Engineering Criteria for Nuclear Power Plants. 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. It is also the intent of this plan to make information about regulatory matters widely available and to improve communication between the NRC. Section 2. “Interim Staff Guidance on Seismic Issues Associated with High Frequency Ground Motion in Design Certification and Combined License Applications” (Ref. The NRC may neither conduct nor sponsor.
Specifically. or combined construction and operating licenses (COLs). and leading to the establishment of a Safe Shutdown Earthquake (SSE) to satisfy the design requirements of Appendix S to 10 CFR Part 50. That guide provides general guidance on methods acceptable to the NRC staff for: (1) conducting geological. DISCUSSION Reason for Change The changes in this revision (Revision 2) reflect the applicability of RG 1. . According to Appendix S to 10 CFR Part 50. however.1 g. and geotechnical investigations. Background The NRC staff has used the 1973 version of RG 1. such as PSHA. 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. (4) determining seismic wave transmission (soil amplification) characteristics of soil and rock sites. Equipment and Systems.” of NUREG-0800. the CSDRS for several new reactor designs are derived from RG 1. “Design of Structures. and (d)(2) of 10 CFR 100. however. update of the discussion in the Implementation section. ISG-017 supplements the guidance provided in NUREG-0800 and states that RG 1.60.1 g. Components. insertion of text in the Introduction explaining the purpose of regulatory guides.60 is no longer used to characterize the hazard for the seismic design of nuclear power plants. requires. (2) identifying and characterizing seismic sources. (d)(1). “Geologic and Seismic Siting Criteria.60 spectral values are based on deterministic values for western United States earthquakes. 1997. updated glossary. and Regulatory Position 5. The steps necessary to develop the final SSE are described in Chapter 3.23. the explicit consideration of the uncertainties associated with geological and seismological characteristics through an appropriate analysis.4 of RG 1. 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. geophysical. the foundation level ground motion must be represented by an appropriate response spectrum with a peak ground acceleration of at least 0. the Paperwork Reduction Act. anchored at 0.” The new siting regulation. It forms part of the licensing basis for nuclear power plants constructed during the 1970s and 1980s. which applies to new reactors as well as nuclear power plant construction permits or operating licenses on or after January 10.60 to the 10 CFR Part 52 licensing framework for new reactors. The new reactors. the text of the footnote on the first page. utilize other methods for determining the design response spectra through the calculation of the ground motion response spectra (GMRS) for early site permits (ESPs). and inclusion of the accession numbers for the NRC’s Agencywide Documents Access and Management System (ADAMS) in the reference section.23. which was subsequently withdrawn and replaced by RG 1. and (5) determining a site-specific. Although RG 1.60 spectra with modified control points to broaden the spectra in the higher frequency range. RG 1.165 (Ref.B. performancebased GMRS. in part.60 for numerous siting and licensing activities since its initial publication and it has also been used effectively by both domestic and international stakeholders. seismological. The role of PSHA also led to the development of RG 1. 8).208 provides a detailed description of the development of the final SSE. 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. satisfying the requirements of paragraphs (c). Other changes included updated reference materials.208 in 2007. (3) conducting a probabilistic seismic hazard assessment (PSHA).
the maximum ground acceleration line represents the Design Response Spectra. The horizontal component Design Response Spectra in Figure 1 of this guide correspond to a maximum horizontal ground acceleration of 1. that is. such as being underlain by poor soil deposits.0 g. The response spectra developed for a site are known as the Design Response Spectra. 10. 10. Blume and Kapur (Ref.5 cps (control point C) and are shown at the top. specifies a number of required investigations for determining the SSE. The Horizontal Component .Response Spectra Shapes Appendix A to 10 CFR Part 100. In this procedure. 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 1.25 cycles per second (cps) or Hertz (Hz) (control point D) to a frequency of 2. 11 and 12). The velocity region lines slope downward from a frequency of 0. the Design Response Spectra should be linearly scaled from Figures 1 and 2 in proportion to the specified maximum horizontal ground acceleration. However. 1. constitute the acceleration region of the horizontal Design Response Spectra.0 g. The horizontal and vertical component Design Response Spectra in Figures 1 and 2. but does not give a specific method for defining the response spectra. The Design Response Spectra can be developed statistically from response spectra of past strong-motion earthquakes. The remaining two sets of lines between the frequencies of 2. Blume. 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. 9.The numerical values of design displacements. The recorded ground accelerations and response spectra of past earthquakes provide a basis for the design of structures to resist earthquakes. modification to this procedure will be required. and the middle part depends on the maximum velocity. the Design Response Spectra should be developed individually according to the site characteristics. respectively. with a break at a frequency of 9 cps (control point B). the base diagram consists of three parts: the bottom line on the left part represents the maximum ground displacement. 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. are designed to sustain and remain functional. which now applies only to an operating license applicant or holder whose construction permit was issued prior to January 10. 9 as well as Figure 9 of Ref. 1997. and is set at 36 inches for a ground acceleration of 1. the bottom line on the right part represents the maximum acceleration. These shapes agree with those developed by Newmark. . the potential maximum earthquake for which structures. The maximum ground displacement is taken proportional to the maximum ground acceleration. and Kapur and shown in Figure 15 of Ref. In Figure 1. 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. 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. as was done by Newmark.5 cps and 33 cps (control point A). velocities. For frequencies higher than 33 cps. for unusually soft sites. After reviewing these documents. systems. For sites with different acceleration values specified for the design earthquake. and components important to safety. the procedure described above will not apply.0 g. Appendix A requires developing response spectra corresponding to the expected maximum ground acceleration for a site. In these cases. of this guide correspond to a maximum horizontal ground acceleration of 1.
5 2.5 cps) D (0. .61 3. Horizontal Design Response Spectra Relative Values of Spectrum Amplification Factors for Control Points Percent of Critical Damping 0.28 1.25 2.54 4.05 1.27 2. Maximum ground displacement is taken proportional to maximum ground acceleration.0 4.70 a.0 1. for ground acceleration of 1.96 5.0 7.0 2.20 1.b A (33 cps) B (9 cps) C (2.0 5.0 10.0 Amplification Factors for Control Points Accelerationa.72 1.Table 1. and is 36 in.90 2. Acceleration and displacement amplification factor are taken from recommendations given in Reference 9.0 2.13 2.50 1.b Displacementa.0 gravity. b.25 cps) 1.95 3.0 3.88 1.
Horizontal Design Response Spectra Scaled to 1 g Horizontal Ground Acceleration .Figure 1.
whereas displacement amplification factors are 2/3 those for horizontal design response spectra. 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 2. velocities. Maximum ground displacement is taken proportional to maximum ground acceleration and is 36 in. for ground acceleration of 1.90 C (3. .5 cps) 5.67c 4. Construction of the spectral shapes in Figure 2 followed the instructions in references 7 and 8 for the construction of vertical component spectra. The vertical component Design Response Spectra corresponding to the maximum horizontal ground acceleration of 1. constitute the acceleration region of the vertical Design Response Spectra.25 1.25 cps (control point D) to a frequency of 3. b.The numerical values of design displacements.37 1.0 5.b A (33 cps) 1. and accelerations in these spectra are obtained by multiplying the corresponding values of the maximum horizontal ground motion (acceleration = 1.b Displacementa. c.0 1. they are the same.0 1.25 cps) 2.0 g and displacement = 36 in.5 cps and 33 cps (control point A).96 3. Table 2.59 2.0 gravity.17 D (0.54 2.5.0 1.0 7.0 g are shown in Figure 2 of this guide.25 and 3. For frequencies higher than 33 cps.0 1.05 2. with a break at the frequency of 9 cps (control point B). Acceleration amplification factors for the vertical design response spectra are equal to those for horizontal design response spectra at a given frequency.5 cps (control point C) and are shown at the top. the Design Response Spectra follow the maximum ground acceleration line. Vertical Design Response Spectra Relative Values of Spectrum Amplification Factors for Control Points Percent of Critical Damping 0.0 B (9 cps) 4. The velocity region lines slope downward from a frequency of 0.) by the factors given in Table 2 of this guide.0 10. These values were changed to make this table consistent with the discussion of vertical components in Section B of this guide.0 Amplification Factors for Control Points Accelerationa.2.13 a. The remaining two sets of lines between the frequencies of 3. The Vertical Component . It should be noted that the vertical Design Response Spectra values are 2/3 those of the horizontal Design Response Spectra for frequencies less than 0.25.5 2.27 1. which are as described in the following.13 1. for frequencies higher than 3. while the ratio varies between 2/3 and 1 for frequencies between 0.61 2.98 2.5. These ratios between the amplification factors for the two design response spectra are in agreement with those recommended in reference 9.67 1.
Figure 2. Vertical Design Response Spectra scaled to 1 g Horizontal Ground Acceleration .
and the term “applicants” refers to applicants for licenses and permits for (or relating to) nuclear power plants under 10 CFR Parts 50 and 52. unless the licensee makes a change to its licensing basis. 3 In this section.) The applicable multiplication factors and control points are given in Table 2. and Experiments. a linear interpolation should be used. it describes how the NRC staff complies with 10 CFR 50. (Figure 2 is based on a maximum horizontal ground acceleration of 1. The NRC staff does not expect any existing licensee to use or commit to using the guidance in this regulatory guide. without soil-structure interaction effects. D. of the SSE on sites underlain by rock or by soil should be linearly scaled from Figure 12 in proportion to the maximum horizontal ground acceleration specified for the earthquake chosen.) The applicable multiplication factors and control points are given in Table 1.109. and Approvals for Nuclear Power Plants. Licensees may use the information in this regulatory guide for actions which do not require NRC review and approval such as changes to a facility design under 10 CFR 50. and applicants for standard design approvals and standard design certifications under 10 CFR Part 52. “Changes.0 g and accompanying displacement of 36 in. 4 In this section. without soil-structure interaction effects. Use by NRC Staff The NRC staff does not intend or approve any imposition or backfitting of the guidance in this regulatory guide. In addition. a linear interpolation should be used. without the force of a legally binding requirement or an NRC representation of further licensing or enforcement action.59. Methods or solutions that differ from those described in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations.C. The NRC 2 This does not apply to sites which (1) are relatively close to the epicenter of an expected earthquake or (2) which have physical characteristics that could significantly affect the spectral combination of input motion. STAFF REGULATORY GUIDANCE 1. 2.0 g and accompanying displacement of 36 in. The horizontal component ground Design Response Spectra. “licensees” refers to licensees of nuclear power plants under 10 CFR Parts 50 and 52. For damping ratios not included in Figure 2 or Table 2. “Licenses. Certifications.” Licensees may use the information in this regulatory guide or applicable parts to resolve regulatory or inspection issues. IMPLEMENTATION The purpose of this section is to provide information on how applicants and licensees3 may use this guide and information regarding the NRC’s plans for using this regulatory guide. The Design Response Spectra for such sites should be developed on a case-by-case basis. Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged. “voluntary” and “voluntarily” mean that the licensee is seeking the action of its own accord.” Use by Applicants and Licensees Applicants and licensees may voluntarily4 use the guidance in this document to demonstrate compliance with the underlying NRC regulations. of the SSE on sites underlain by rock or by soil should be linearly scaled from Figure 2 in proportion to the maximum horizontal ground acceleration specified for the earthquake chosen. . Tests. “Backfitting” and any applicable finality provisions in 10 CFR Part 52. For damping ratios not included in Figure 1 or Table 1. (Figure 1 corresponds to a maximum horizontal ground acceleration of 1. The vertical component ground Design Response Spectra.
.109(a)(1) or a violation of any of the issue finality provisions in 10 CFR Part 52. However. then the staff may request that the licensee either follow the guidance in this regulatory guide or provide an equivalent alternative process that demonstrates compliance with the underlying NRC regulatory requirements. Examples of such unplanned NRC regulatory actions include issuance of an order requiring the use of the regulatory guide.” (Ref. If a licensee believes that the NRC is either using this regulatory guide or requesting or requiring the licensee to implement the methods or processes in this regulatory guide in a manner inconsistent with the discussion in this Implementation section. unless this regulatory guide is part of the licensing basis for a facility. or guidance if 10 CFR 50. “Management of Facility-Specific Backfitting and Information Collection” (Ref. Additionally. orders.54(f) as to whether a licensee intends to commit to use of this regulatory guide. 13) and the NRC Management Directive 8. If an existing licensee voluntarily seeks a license amendment or change and (1) the NRC staff’s consideration of the request involves a regulatory issue directly relevant to this new or revised regulatory guide and (2) the specific subject matter of this regulatory guide is an essential consideration in the staff’s determination of the acceptability of the licensee’s request. the staff may discuss with licensees various actions consistent with staff positions in this regulatory guide. generic communication. requests for information under 10 CFR 50. “Backfitting Guidelines. then the licensee may file a backfit appeal with the NRC in accordance with the guidance in NUREG-1409. This is not considered backfitting as defined in 10 CFR 50. The NRC staff does not expect or plan to initiate NRC regulatory action which would require the use of this regulatory guide. Such discussions would not ordinarily be considered backfitting even if prior versions of this regulatory guide are part of the licensing basis of the facility. or promulgation of a rule requiring the use of this regulatory guide without further backfit consideration.109(a)(3) applies. the staff may not represent to the licensee that the licensee’s failure to comply with the positions in this regulatory guide constitutes a violation.staff does not expect or plan to request licensees to voluntarily adopt this regulatory guide to resolve a generic regulatory issue. 14).4. as one acceptable means of meeting the underlying NRC regulatory requirement. an existing applicant may be required to comply with new rules. During regulatory discussions on plant specific operational issues.
and statistically combining a number of individual response spectra derived from the records of significant past earthquakes. The SSE for the site is characterized by both horizontal and vertical free-field ground motion response spectra at the free ground surface. the design response spectra acceleration is identical for all damping values and is equal to the maximum (peak) ground acceleration specified for that site. The response spectrum is calculated for a specified vibratory motion input at the oscillators’ supports. Safe Shutdown Earthquake Ground Motion (SSE) is the vibratory ground motion for which certain structures. and components are designed. Response Spectrum means a plot of the maximum response (acceleration. At zero period. Ground Motion Response Spectra (GMRS) are site-specific ground motion response spectra characterized by horizontal and vertical response spectra determined as free-field motions on the ground surface or as free-field outcrop motions on the uppermost in-situ competent material using performancebased procedures. Design Response Spectrum is a relatively smooth relationship obtained by analyzing. pursuant to Appendix S to 10 CFR Part 50. to remain functional. Maximum (peak) Ground Acceleration specified for a given site means that value of the acceleration. systems.GLOSSARY Certified Seismic Design Response Spectra (CSDRS) are site-indpendent seismic design response spectra that have been approved under Subpart B of 10 CFR Part 52 as the seismic design response spectra for an approved certified standard design nuclear power plant. which corresponds to zero period in the design response spectra for that site. or displacement) of a family of idealized single-degree-of-freedom damped oscillators as a function of natural frequencies of the oscillators for a given damping value. The input or control location for the CSDRS is specified in the certified standard design. velocity. evaluating. .
November 1973. Code of Federal Regulations.S. ML13203A236). Blume. Certifications. “Management of Facility-specific Backfitting and Information Collection. NRC. 8. Code of Federal Regulations. “Design Response Spectra for Nuclear Power Plants. Regulatory Guide 1.165. Code of Federal Regulations. 14. “Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion. “Energy. ASCE. Newmark. NRC. pp. ML13207A045). Washington.” Urbana. “Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition. U.. “Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses. and Kanwar K.. U. DC (ADAMS Accession No. California. “Interim Staff Guidance on Seismic Issues Associated with High Frequency Ground Motion in Design Certification and Combined License Applications. Newmark.” American Society of Civil Engineers (ASCE) Structural Engineering Meeting. 2008. “Recommendations for Shape of Earthquake Response Spectra. ML100570203). Title 10. USAEC Contract No. “Licenses. DC (ADAMS Accession No.” Washington.” San Francisco. Washington. (ADAMS Accession No. Washington.” May 19. 2010.S. San Francisco. AT(49-5)-3011. NRC Interim Staff Guidance (ISG) ISG-017. Kapur. and Approvals for Nuclear Power Plants. Title 10. Chapter I. ML081400293) 7. “Reactor Site Criteria. “A Study of Vertical and Horizontal Earthquake Spectra. U. DC. “A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion. Chapter I. M. 6.” Part 100. “Backfitting Guidelines. ML032230247). Chapter I. DC (ADAMS Accession No. ML13203A235). John A. AT(49-5)-2667. Kapur.” Washington. Blume & Associates. NRC. February 1973.4. . (ADAMS Accession No. John A. NRC ISG-01. Illinois.” NUREG–0800. and Kanwar K. WASH-1254. U. Newmark Consulting Engineering Services. “Domestic Licensing of Production and Utilization Facilities Part 50. Blume. N.” Part 52. John A.” NUREG-1409. July 1990. 287-303. 9. DC.” 5. Regulatory Guide 1. USAEC Contract No. “Seismic Design Spectra for Nuclear Power Plants. N. 11. 13. M. N. April 1973.REFERENCES 1. 3.” Journal of The Power Division.” 2.S. Washington. April 1973. 12. Title 10.” NRC Management Directive 8. WASH-1255. Nuclear Regulatory Commission (NRC). DC.” March 24. (ADAMS Accession No. NRC. 10.208. M. ML13207A044). “Energy 4. (ADAMS Accession No. “Energy.S.
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