Seismic Considerations for the Transition Break Size (NUREG-1903)

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Publication Information

Manuscript Completed: February 2008
Date Published: February 2008

Prepared by:
N.C. Chokshi, S.K. Shaukat, A.L. Hiser/U.S. Nuclear Regulatory Commission
G. DeGrassi/Brookhaven National Laboratory
G. Wilkowski/Engineering Mechanics Corporation of Columbus
R. Olson/Battelle
J.J. Johnson/James J. Johnson & Associates

Brookhaven National Laboratory
Building 130
P.O. Box 5000
Upton, NY 11973

Engineering Mechanics Corporation of Columbus
3518 Riverside Drive, Suite 202
Columbus, OH 43221-1735

Battelle
505 King Avenue
Columbus, OH 43201-2693

James J. Johnson & Associates
7 Essex Court
Alamo, CA 94507

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The U.S. Nuclear Regulatory Commission (NRC) has been considering revision of the regulatory requirements for the emergency core cooling system (ECCS), as set forth in Title 10, Section 50.46, of the Code of Federal Regulations (10 CFR 50.46); Appendix K to 10 CFR Part 50; and General Design Criterion (GDC) 35. In particular, those requirements state that the ECCS shall be sized to provide adequate makeup water to compensate for a break of the largest diameter pipe in the primary system [i.e., the so-called "double-ended guillotine break" (DEGB)]. Consequently, in order to risk-inform the break size, the staff of the NRC proposed the concept of transition break size (TBS). In addition, the NRC developed pipe break frequencies as a function of break size using an expert elicitation process for degradation-related pipe breaks in reactor coolant systems of typical boiling- and pressurized-water reactors. That elicitation focused on determining event frequencies that initiate by unisolable primary side failures that can be exacerbated by material degradation with age under normal operating conditions. The purpose of this study was to assess potential seismic effects on the postulated TBS, and to provide information to facilitate review and comment regarding the proposed risk-informed revision of ECCS requirements in 10 CFR 50.46. Thus, this report evaluates the seismic effects, using different approaches to evaluate flawed and unflawed piping, and indirect failures of other components and component supports that could lead to piping failure.