Published March 1989 | Version v1
Report

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).

Optional Information

Secondary number(s)
CONF-8810155--Vol.1.