Potential application of NRC aging research to license renewal
Creators
Description
A strong technical base, when developed and implemented, to manage aging in plant safety related systems, support systems, structures, and components will give confidence to all of them in the nuclear community toward the continuous safe operation of nuclear power plants of all ages. The following specific Nuclear Plant Aging Research programs, implemented by the Division of Engineering of the Office of Nuclear Regulatory Research, address the technical safety issues related to aging and will provide the technical bases for the development of regulatory guides and review procedures for license renewal applications. These programs are (1) risk significance of component aging and prioritization, (2) hardware-oriented engineering programs for electrical and mechanical components, safety systems, and support systems; primary system pressure boundary components and materials and nondestructive examination; and civil structures, (3) reviews of technical specifications from the standpoint of aging, (4) development of guidance for recordkeeping to track and evaluate aging impacts, (5) residual lifetime evaluation and development of guidance for aging mitigation of large LWR components and structures, and (6) development of regulatory guides and review procedures for license renewal applications. This paper provides an overview of the intended application of plant aging research results. In the process it delineates some key steps recommended for the development of appropriate regulatory guides and review procedures involving the technical issues for license renewal considerations
Additional details
Publishing Information
- Imprint Title
- Sixteenth water reactor safety information meeting. Volume 1: Plenary session, Decontamination and decommissioning, License renewal, Human factors, generic issues, Risk analysis/PRA applications, Innovative concepts for increased safety of advanced power reactors
- Imprint Pagination
- 561 p.
- Journal Page Range
- p. 141-162.
- Report number
- NUREG/CP--0097-Vol.1
Conference
- Title
- 16. water reactor safety information meeting.
- Dates
- 24-27 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22019077
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CORROSION; CRACK PROPAGATION; CRACKS; DOCUMENTATION; FATIGUE; INSPECTION; LIFETIME; MANAGEMENT; MECHANICAL STRUCTURES; MITIGATION; MONITORING; NONDESTRUCTIVE TESTING; PIPES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR LICENSING; REACTOR MAINTENANCE; REACTOR MATERIALS; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SAFETY ENGINEERING; SHIPPINGPORT REACTOR; SPECIFICATIONS; TIME DEPENDENCE; US NRC
- Descriptors DEC
- CHEMICAL REACTIONS; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; LICENSING; MAINTENANCE; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8810155--Vol.1.