BWR reactor pressure vessel license renewal industry report; revision 1. Final report
- 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
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Related Subjects
210100
210700
BWR TYPE REACTORS
CORROSION
CORROSION FATIGUE
EMBRITTLEMENT
EPRI
FLANGES
IN-SERVICE INSPECTION
INSPECTION
LICENSING REGULATIONS
MAINTENANCE
NOZZLES
NUCLEAR POWER
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
PRESSURE VESSELS
RADIOLYSIS
REACTOR COMPONENTS
REACTOR LICENSING
REACTOR VESSELS
REGULATION AND LICENSING
REGULATIONS
SAFETY
SERVICE LIFE
STRESS RELAXATION