New time-line technique for station blackout core-melt analysis

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6993022

Stutzke, M A

Florida Power Corporation (FPC) has developed a new method for analyzing station blackout (SBO) core-melt accidents. This method, created during the recent probabilistic risk assessment (PRA) of Crystal River Unit 3 (CR-3), originated from the need to analyze the interactions among the two-train emergency feedwater (EFW) system, station batteries, and diesel generators (DGs) following a loss of off-site power (LOSP) event. SBO core-melt sequences for CR-3 are unique since the time core-melt commences depends on which DG fails last. The purpose of this paper is to outline the new method of analysis of SBO core-melt accidents at CR-3. The significance of SBO core-melt accidents to total plant risk, along with the efficacy of various methods to reduce SBO risk, are also discussed.

• Research Organization: Florida Power Corp., St. Petersburg
• OSTI ID: 6993022
• Report Number(s): CONF-861102-; TRN: 87-008113
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CRYSTAL RIVER-3 REACTOR
OUTAGES
REACTOR CORE DISRUPTION
PROBABILITY
AC SYSTEMS
AFTER-HEAT REMOVAL
ELECTRIC GENERATORS
FEEDWATER
MELTDOWN
REACTOR ACCIDENTS
RHR SYSTEMS
RISK ASSESSMENT
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
POWER REACTORS
POWER SYSTEMS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled