Seismic Analysis Issues in Design Certification Applications for New Reactors
The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of several seismic analysis issues encountered during a review of recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
- DOE Contract Number:
- DE-AC02-98CH10886
- OSTI ID:
- 1015138
- Report Number(s):
- BNL-95100-2011-CP; TRN: US1102808
- Resource Relation:
- Conference: ASME 2011 Pressure Vessels & Piping Division PVP2011 ; Baltimore, MD; 20110717 through 20110717
- Country of Publication:
- United States
- Language:
- English
Similar Records
Report on Lessons Learned from the NP 2010 Early Site Permit Program FINAL REPORT
The System 80+ Standard Plant design control document. Volume 3