The use of NPAR (Nuclear Plant Aging Research) results in plant inspection activities
Conference
·
OSTI ID:5321857
The US NRC's Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describes the NPAR information which can enhance inspection activities, and provides a mechanism for making pertinent research available to the inspectors. 7 refs., 2 figs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5321857
- Report Number(s):
- BNL-NUREG-42936; CONF-8910222-12; ON: DE90004954; TRN: 90-004056
- Resource Relation:
- Conference: 17. water reactor safety information meeting, Rockville, MD (USA), 23-25 Oct 1989
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results from the Nuclear Plant Aging Research Program: Their use in inspection activities
Nuclear Plant Aging Research (NPAR) program plan
Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports
Technical Report
·
Sat Sep 01 00:00:00 EDT 1990
·
OSTI ID:5321857
Nuclear Plant Aging Research (NPAR) program plan
Technical Report
·
Sat Jun 01 00:00:00 EDT 1991
·
OSTI ID:5321857
Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports
Technical Report
·
Wed Dec 01 00:00:00 EST 1993
·
OSTI ID:5321857
+2 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AGING
INSPECTION
BWR TYPE REACTORS
PWR TYPE REACTORS
COMPLIANCE
DESIGN
FAILURE MODE ANALYSIS
INTERFACES
MONITORING
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR SAFETY
RECOMMENDATIONS
REGULATIONS
REPORTING REQUIREMENTS
RESEARCH PROGRAMS
TECHNOLOGY ASSESSMENT
THERMAL DEGRADATION
MAINTENANCE
OPERATION
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AGING
INSPECTION
BWR TYPE REACTORS
PWR TYPE REACTORS
COMPLIANCE
DESIGN
FAILURE MODE ANALYSIS
INTERFACES
MONITORING
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR SAFETY
RECOMMENDATIONS
REGULATIONS
REPORTING REQUIREMENTS
RESEARCH PROGRAMS
TECHNOLOGY ASSESSMENT
THERMAL DEGRADATION
MAINTENANCE
OPERATION
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled