Published 2004 | Version v1
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Overview of the age-related degradation of nuclear power plant structures

Creators

  • 1. Bechtel Corporation, San Francisco, CA (United States)

Description

License renewal of nuclear power plants is an issue of increasing interest to the U.S. nuclear industry and the U.S. NRC. This paper presents and evaluates the plausible age-related degradation mechanisms that may affect the concrete and steel containment structures and other Class I structures to continue to perform their safety functions. Preventive and/or mitigative options are outlined for managing degradation mechanisms that could significantly affect plant performance during the license renewal period. The provided technical information and the degradation management options may be used as references for comparison with plant specific conditions to ensure that age-related degradation is controlled during the license renewal term. Plausible degradation mechanisms described and analyzed as they may affect the concrete, reinforcing steel, containment steel shell, prestressed-tendon, steel liner and other structural components typically used in Class I structures. The significance of these age-related degradation mechanisms to the structural components are evaluated, giving consideration to the design basis and quality of construction; typical service conditions; operating and maintenance history; and current test, inspection and refurbishment practices for containment and Class I structures. Degradation mechanisms which cannot be generically dispositioned on the basis of the two-step approach: (1) they will not cause significant degradation, or (2) any potential degradation will be bounded by current test, inspection, analytical evaluation, and/or refurbishment programs are identified. Aging degradation management measures are recommended to address the remaining age-related degradation mechanisms. A three-phase approach for the management of the containment and Class I structures is introduced. Various techniques, testing tools and the acceptable criteria for each step of the evaluation of the structures status are provided. The preventive and mitigative measures to limit further degradation are also provided. (author)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1

Additional details

Publishing Information

Imprint Title
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1
Imprint Pagination
772 p.
Journal Page Range
p. 7C1-7C6
Report number
INIS-XA-N--080

Conference

Title
4. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
5-8 Apr 1994
Place
Taipei, Taiwan (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35095486
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; LICENSING PROCEDURES; NUCLEAR POWER PLANTS; REACTOR COMPONENTS; REACTOR MAINTENANCE; REACTOR SAFETY; THERMAL DEGRADATION
Descriptors DEC
ADMINISTRATIVE PROCEDURES; MAINTENANCE; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS

Optional Information

Notes
16 refs