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

Technical Report · Fri Jul 01 04:00:00 EDT 1994

OSTI ID:10121151

Schwirian, R ^[1]; Robison, G ^[2]

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1. Westinghouse Electric Co., Monroeville, PA (United States)
2. Duke Power Co., Charlotte, NC (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). Pressurized water reactor (PWR) reactor pressure vessel (RPV) internals designed by all three U.S. PWR nuclear steam supply system vendors have been evaluated relative to the effects of age-related degradation mechanisms; the capability of current design limits; inservice examination, testing, repair, refurbishment, and other programs to manage these effects; and the assurance that these internals can continue to perform their intended safety functions in the license renewal term. This industry report (IR), one of a series of ten, provides a generic technical basis for evaluation of PWR reactor pressure vessel internals for license renewal.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Westinghouse Electric Corp., Monroeville, PA (United States); Duke Power Co., Charlotte, NC (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 10121151
• Report Number(s): EPRI-TR--103838; ON: UN95007584
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
210700
CORROSION
CORROSION FATIGUE
EMBRITTLEMENT
EPRI
IN-SERVICE INSPECTION
LICENSING REGULATIONS
MAINTENANCE
NUCLEAR POWER
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE VESSELS
PWR TYPE REACTORS
RADIOLYSIS
REACTOR COMPONENTS
REACTOR LICENSING
REGULATION AND LICENSING
SAFETY
SERVICE LIFE
STRESS RELAXATION