BWR containments license renewal industry report; revision 1. Final report

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

OSTI ID:10121158

Smith, S; Gregor, F ^[1]

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1. MDC-Ogden Environmental and Energy Services Co., Inc., Southfield, MI (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 (IR`s). License renewal applicants may choose to reference these IR`s in support of their plant-specific license renewal applications as an equivalent to the integrated plant assessment provisions of the license renewal rule (IOCFR54). The scope of the IR provides the technical basis for license renewal for U.S. Boiling Water Reactor (BWR) containments. The scope of the report includes containments constructed of reinforced or prestressed concrete with steel liners and freestanding stell containments. Those domestic BWR containments designated as Mark I, Mark II or Mark III are covered, but no containments are addressed before these designs. The report includes those items within the jurisdictional boundaries for metal and concrete containments defined by Section III of the ASME Boiler and Pressure Vessel Code, Division 1, Subsection NE (Class MC) and Division 2 (Class CC) and their supports, but excluding snubbers.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 10121158
• Report Number(s): EPRI-TR-103840; ON: UN95007583; TRN: 95:002360
• Resource Relation: Other Information: PBD: Jul 1994
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESTRESSED CONCRETE
CORROSION
REACTOR COMPONENTS
INSPECTION
BWR TYPE REACTORS
LICENSING REGULATIONS
CONTAINMENT SHELLS
CONTAINMENT BUILDINGS
STEELS
LINERS
SUPPORTS
EPRI
NUCLEAR POWER
SAFETY
REACTOR LICENSING
RADIOLYSIS
WEATHERING
STRESS CORROSION
THERMAL DEGRADATION
210100
210700
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REGULATION AND LICENSING