Air operated valve maintenance at Bruce 'A'
Description
In 1990, a new Air Operated Valve(AOV) diagnostic tool was demonstrated at Bruce A. During the demonstration, the diagnostic unit quickly and correctly identified a passing valve that had extended a unit outage by five days. As a result of the demonstration, Bruce A began a pilot program in 1991 to assess the condition of critical station AOV's and to lay down the framework for developing an AOV Preventive Maintenance (PM) program through the use of state of the art valve diagnostics. This paper will begin by focusing on the key elements of the program including program goals, division of responsibilities, work flow and quality assurance. The focus will then shift to a discussion of the results of over 1000 diagnostic tests that have been performed at Bruce A. The trends observed in the results will be explored to identify those areas of AOV maintenance which should be targeted. The data will also be analyzed to demonstrate the effectiveness of the program in the areas of reduced corrective maintenance and reduced maintenance rework. The results of recent program review are also presented to complete the discussion of the program's effectiveness
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29054783.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the third international conference on CANDU maintenance
- Imprint Pagination
- 473 p.
- Journal Page Range
- p. 79-85
- Report number
- INIS-CA--0018
Conference
- Title
- 3. International conference on CANDU maintenance
- Dates
- 19-21 Nov 1995
- Place
- Toronto, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 29054783
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRUCE-1 REACTOR; BRUCE-2 REACTOR; BRUCE-3 REACTOR; BRUCE-4 REACTOR; CALIBRATION; COMPUTERIZED CONTROL SYSTEMS; FLOWMETERS; INSPECTION; MAINTENANCE; NONDESTRUCTIVE TESTING; PORTABLE EQUIPMENT; QUALITY CONTROL; REACTOR SAFETY; SAFETY ANALYSIS; SAFETY ENGINEERING; VALVES
- Descriptors DEC
- CANDU TYPE REACTORS; CONTROL; CONTROL EQUIPMENT; CONTROL SYSTEMS; EQUIPMENT; FLOW REGULATORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS TESTING; MEASURING INSTRUMENTS; NATURAL URANIUM REACTORS; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS
Optional Information
- Notes
- 6 refs., 4 figs.