Published 1996 | Version v1
Report Restricted

The use of check valve performance data to support new concepts (probabilistic risk assessment, condition monitoring) for check valve program

Description

The concept of developing an integrated check valve database based on the Nuclear Power Reliability Data System (NPRDS) data was presented at the last Symposium. The Nuclear Industry Check Valve Group (NIC), working in cooperation with the Oak Ridge National Laboratory (ORNL), has completed an operational database of check valve performance from 1984 to the present. NIC has committed to the nuclear industry to periodically update the data and maintain this information accessible. As the new concepts of probabilistic risk analysis and condition monitoring are integrated into the American Society of Mechanical Engineers (ASME) Code, a critical element will be performance data. From check valve performance data, feasible failure modes and rates can be established. When a failure rate or frequency of failures can be established based on a significant enough population (sampling), a more solid foundation for focusing resources and determining appropriate frequencies and testing can be determined. The presentation will give the updated status of the NIC Check Valve Performance Database covering (1) methodology used to combine the original ORNL data; (2) process/controls established for continuing update and refinement of the data; (3) discussion of how this data is being utilized by (a) OM-22 for condition monitoring, and (b) risk-based inservice testing work of Westinghouse Owners' Group; and (4) results/trends of data evaluations. At the 1994 Symposium, ORNL provided an update as of 1991 to their original work of 1984 -1990 which they had performed to characterize check valve degradations and failures in the nuclear industry. These characterizations will be updated to 1995 and additional reviews provided to give insight into the current condition and trends of check valve performance

Files

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Additional details

Publishing Information

Imprint Title
Proceedings of the 4th NRC/ASME symposium on valve and pump testing
Imprint Pagination
719 p.
Journal Page Range
p. 2B.25-2B.33.
Report number
NUREG/CP--0152

Conference

Title
4. NRC/ASME symposium on valve and pump testing in nuclear power plants.
Dates
15-18 Jul 1996.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28013967
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA BASE MANAGEMENT; HISTORICAL ASPECTS; IN-SERVICE INSPECTION; MONITORING; NUCLEAR POWER PLANTS; PERFORMANCE; REVIEWS; RISK ASSESSMENT; VALVES
Descriptors DEC
CONTROL EQUIPMENT; DOCUMENT TYPES; EQUIPMENT; FLOW REGULATORS; INSPECTION; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-9607103--.