Critical safety parameters: The logical approach to refresher training
Description
Nuclear power plant managers must ensure that control room staff are able to perform effectively. This is of particular importance through the longer term after initial authorization. Traditionally refresher training has been based on delivery of fragmented training packages typically derived from the initial authorization training programs. Various approaches have been taken to provide a more integrated refresher training program. However, methods such as job and task analysis and subject matter expert derived training have tended to develop without a focused clear overall training objective. The primary objective of all control room staff training is to ensure a proper and safe response to all plant transients. At the Point Lepreau Nuclear Plant, this has defined the Critical Safety Parameter based refresher training program. The overall objective of the Critical Safety Parameter training program is to ensure that control room staff can monitor and control a discrete set of plant parameters. Maintenance of the selected parameters within defined boundaries assures adequate cooling of the fuel and containment of radioactivity. Control room staff need to be able to reliably respond correctly to plant transients under potentially high stress conditions,. utilizing the essential knowledge and skills to deal with such transients. The inference is that the knowledge and skills must be limited to that which can be reliably recalled. This paper describes how the Point Lepreau Nuclear Plant has developed a refresher training program on the basis of a limited number of Critical Safety Parameters. Through this approach, it has been possible to define the essential set of knowledge and skills which ensures a correct response to plant transients
Additional details
Publishing Information
- Imprint Title
- Proceedings of the ninth symposium on the training of nuclear facility personel
- Imprint Pagination
- 623 p.
- Journal Page Range
- p. IV.B.3.1-IV.B.3.23.
- Report number
- CONF-9104135--
Conference
- Title
- 9. symposium on the training of nuclear facility personnel.
- Dates
- 14-18 Apr 1991.
- Place
- Denver, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008817
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVITY LEVELS; AUXILIARY SYSTEMS; CANADA; CONTAINMENT SYSTEMS; CONTROL; CONTROL ROOMS; DETECTION; ECCS; EDUCATION; EMERGENCY PLANS; FEEDWATER; HEAT SINKS; HUMAN FACTORS; MAINTENANCE; MODERATORS; MONITORING; NUCLEAR POWER PLANTS; POINT LEPREAU-1 REACTOR; POINT LEPREAU-2 REACTOR; POWER DISTRIBUTION; PRESSURE MEASUREMENT; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR SHUTDOWN; RELIABILITY; RESPONSE FUNCTIONS; STEAM GENERATORS; SUBCOOLING; TEMPERATURE MEASUREMENT; TRANSIENTS; VOLUME
- Descriptors DEC
- BOILERS; CANDU TYPE REACTORS; CONTAINMENT; COOLING; COOLING SYSTEMS; DEVELOPED COUNTRIES; DISTRIBUTION; FUNCTIONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; NATURAL URANIUM REACTORS; NORTH AMERICA; NUCLEAR FACILITIES; OPERATION; OXYGEN COMPOUNDS; PERSONNEL; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SHUTDOWN; SPATIAL DISTRIBUTION; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER