Incorporation of new procedures into the Limerick PRA
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6753585
When the Limerick probabilistic risk assessment (LGS PRA) was first published, the plant was still under construction and there were no station emergency operating procedures available to the analysts. The Limerick transient response implementation plan (TRIP) procedures were later written utilizing the symptom-based emergency procedure guidelines developed by the boiling water reactor owners group. As part of its program to use the PRA as a living plant model, Philadelphia Electric Company undertook a project to determine to what extent the existing model incorporated the operator actions called or by the TRIP procedures and, where there were differences, to modify the LGS PRA model. The analysis of the TRIP procedures was conducted along the general guidelines for the analysis of human interactions provided by the systematic human action reliability procedures (SHARP).
- Research Organization:
- Philadelphia Electric Co., PA
- OSTI ID:
- 6753585
- Report Number(s):
- CONF-861102-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
- Country of Publication:
- United States
- Language:
- English
Similar Records
Review insights on the probabilistic risk assessment for the Limerick Generating Station
Limerick probabilistic risk analysis highlights
Use of plant-specific PRA in an EOP scope audit
Technical Report
·
Wed Aug 01 00:00:00 EDT 1984
·
OSTI ID:6776445
Limerick probabilistic risk analysis highlights
Conference
·
Fri Dec 31 23:00:00 EST 1982
· Proc. Am. Power Conf.; (United States)
·
OSTI ID:6686565
Use of plant-specific PRA in an EOP scope audit
Conference
·
Mon Dec 31 23:00:00 EST 1990
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5854460
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
DECISION MAKING
ECCS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ERRORS
FAILURE MODE ANALYSIS
FAILURES
HIGH PRESSURE COOLANT INJECTION
HUMAN FACTORS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
POWER REACTORS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
DECISION MAKING
ECCS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ERRORS
FAILURE MODE ANALYSIS
FAILURES
HIGH PRESSURE COOLANT INJECTION
HUMAN FACTORS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
POWER REACTORS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS