Qualification Testing Evaluation (QTE) program for safety-related equipment

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:6277220

Bonzon, L. L.; Gillen, K. T.; Clough, R. L.; Salazar, E. A.; Buckalew, W. H.; Thome, F. V.; Stuetzer, O. M.; Feit, R.

The nuclear power industry is required to demonstrate that certain safety-related equipment is ''qualified'' and will function even in the event of a severe reactor accident. Demonstration of qualification by testing is the preferred approach. International interest in equipment qualification, and its recognition as being paramount to safety, is rapidly increasing, with most major supplier-countries developing sophisticated qualification testing facilities. An aspect of the demonstration of qualification is to assure that the qualification testing applied to safety-related equipment is both realistic and conservative; that is, a program of qualification methodology assessment and improvement is imperative. In the United States, the Nuclear Regulatory Commission (NRC) is sponsoring the Qualification Testing Evaluation Program with the goal of obtaining data that will confirm or improve the technical bases for equipment qualification programs. This multi-task Program has long-term, continuing objectives, but recent new results have been obtained and these results are being incorporated into NRC regulations with attendant impact on the nuclear industry. 19 refs. (JDB)

• Research Organization: Sandia National Labs., Albuquerque, NM (USA); Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6277220
• Report Number(s): SAND-80-0544C; IAEA-CN-39/104; CONF-801056-4; ON: TI85016663
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR ACCIDENTS
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SIMULATION
SYSTEMS ANALYSIS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS