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U.S. Department of Energy
Office of Scientific and Technical Information

BWR reactor pressure vessel license renewal industry report; revision 1. Final report

Technical Report ·
OSTI ID:10121118
;  [1]
  1. General Electric Co., San Jose, CA (United States)

The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures and components, in the license renewal technical Industry Reports (IRs). License renewal applicants may choose to reference these IRs in support of their plant-specific license renewal applications, as an equivalent to the integrated plant assessment provisions of the license renewal rule (10 CFR Part 54). The scope of the IR provides the technical basis for license renewal for U.S. Boiling Water Reactor (BWR) Reactor Pressure Vessels (RPVs). The report includes the following RPV components: attachment welds, closure studs, nozzles and safe ends, penetrations, vessel shell and flanges, top and bottom heads and vessel support skirt. The scope is limited to domestic BWRs designated by GE Nuclear Energy as BWR/2 through BWR/6.

Research Organization:
Electric Power Research Inst., Palo Alto, CA (United States); General Electric Co., San Jose, CA (United States)
Sponsoring Organization:
Electric Power Research Inst., Palo Alto, CA (United States)
OSTI ID:
10121118
Report Number(s):
EPRI-TR--103836; ON: UN95007572
Country of Publication:
United States
Language:
English