Published 1996 | Version v1
Miscellaneous Open

Equipment qualification testing - a practical approach

  • 1. Mu-Sigma Consulting Engieners and Laoratories (MEC), Mississauga, ON (Canada)

Description

When nuclear safety equipment is credited with a Required Safety Function it must properly perform that function to facilitate safe control and/or shutdown of the plant during a design basis accident. When such equipment is required to be environmentally (EQ) and/or seismically qualified (SQ) for safety related use in CANDU nuclear power plants, the preferred method of qualification is by type testing. The qualification testing process requires that the test specimen equipment be subjected to the aging stressors associated with the normal service conditions that it would experience during it's required qualified (or service) life. Following the aging process, the test specimen is in a condition representative of that in which it would be at the end of its service life in the plant. The test specimen is then subjected to a simulated accident during which it must satisfy performance requirements thereby demonstrating that it can perform its required safety function. The performance requirements specified for the qualification testing must be designed to ensure that satisfactory performance of the safety function is demonstrated during the qualification program. This paper provides descriptions of practical methods used in the deriving and satisfying of relevant performance requirements during the qualification testing of safety related equipment. (author)

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Part of:
Proceedings of the seventeenth annual Canadian Nuclear Society conference

Additional details

Publishing Information

Imprint Title
Proceedings of the seventeenth annual Canadian Nuclear Society conference
Imprint Pagination
820 p.
Journal Page Range
v. 2 [16 p.]
Report number
INIS-CA--0066(v.1,2)

Conference

Title
17. annual Canadian Nuclear Society conference
Dates
9-12 Jun 1996
Place
Fredericton, NB (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
30032418
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL SYSTEMS; DESIGN BASIS ACCIDENTS; PERFORMANCE TESTING; QUALITY ASSURANCE; REACTOR ACCIDENTS; REACTOR SAFETY; SERVICE LIFE; SIMULATION; SYSTEMS ANALYSIS; VALVES
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; LIFETIME; REACTOR ACCIDENTS; SAFETY; TESTING

Optional Information

Notes
9 refs., 2 tabs., 11 figs.