Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water reactor building internal structure and steam generator.

Issue Section:
Research Papers
Topics:
Boilers, Heavy water reactors, Nuclear power stations, Seismic analysis
1.
ASCE-4, 1986, ASCE Standard, “Seismic Analysis of Safety Related Nuclear Structures and Commentary on Standard of Seismic Analysis of Safety Related Structures.”
2.
Reddy
G. R.
, et al.,
1994
, “
Procedure of Applying Decoupling for Complex Primary and Secondary Systems
,” Seismic Engineering Conference Proceedings,
ASME PVP
-Vol.
275-1
, pp.
129
–
139
.
3.
United States Nuclear Regulatory Commission (USNRC), 1990, Standard Review Plan (SRP), Section 3.7.2, “Seismic System Analysis.”
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