Management experience using a novel probabilistic risk assessment format for safety communication
- Pickard, Lowe and Garrick, Inc., Newport Beach, CA (United States)
- Dept. of Energy, Aiken, SC (United States)
- Houston Lighting and Power Co., Bay City, TX (United States)
- Stone and Webster Engineering Corporation, Aiken, SC (United States)
In order to independently assess the effectiveness of the Savannah River Site (SRS) restart test program using level 1 probabilistic risk assessment (PRA) logic, it was necessary that the PRA logic be reformatted in a manner that could facilitate usage as a process tool. The US Department of Energy (DOE) management elected to develop a new top-down presentation format for the existing K-reactor PRA. Despite the availability of the PRA, its widespread use for evaluating safety was hampered by the mystique surrounding its traditional presentation of models and results. The DOE desired a format that could speak clearly to engineers, scientists, and managers who have not directly participated in the PRA and who may not be intimately familiar with the design and operation of the SRS reactors. Similar needs led South Texas Project (STP) to pursue a program to provide summary information about the plant safety capabilities that were integrated from the final safety analysis report (FSAR), PRA, emergency operating procedures, and other sources into an easy-to-use graphic format. The new models represent the hardware and operator actions required to mitigate accident initiating events, as depicted in the STP probabilistic safety assessment (PSA). The models allow important design-basis accidents and core-damage sequences from the PSA to be illustrated in the same format.
- OSTI ID:
- 7055869
- Report Number(s):
- CONF-920606--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 65; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Savannah River Site K-Reactor Probabilistic Safety Assessment
Probabilistic Risk Assessment of disassembly procedures
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANIMALS
COMPUTERS
DIGITAL COMPUTERS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
MAMMALS
MAN
MICROCOMPUTERS
MITIGATION
OPERATION
PERSONAL COMPUTERS
PERSONNEL
POWER REACTORS
PRIMATES
PROBABILISTIC ESTIMATION
PRODUCTION REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTOR START-UP
REACTORS
RISK ASSESSMENT
SAFETY
SAFETY ANALYSIS
SOUTH TEXAS PROJECT-1 REACTOR
SOUTH TEXAS PROJECT-2 REACTOR
SPECIAL PRODUCTION REACTORS
START-UP
TESTING
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
VALIDATION
VERTEBRATES
WATER COOLED REACTORS
WATER MODERATED REACTORS