An IPE back-end study for Turkey Point plant
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7022213
- Florida Power and Light Co., Juno Beach (United States)
This paper describes a study of Turkey Point plant's large dry containment as part of a response to the US Nuclear Regulatory Commission's individual plant examination Generic Letter 88-20. Two unique features of Turkey Point containment are discussed. This study includes an evaluation of the containment response to the physical processes occurring during an accident and probabilistic analysis of the spectrum of severe-accident progressions.
- OSTI ID:
- 7022213
- Report Number(s):
- CONF-911107-; CODEN: TANSA; TRN: 92-030844
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TURKEY POINT-3 REACTOR
RISK ASSESSMENT
TURKEY POINT-4 REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
DAMAGE
DRAINAGE
ECCS
FAILURE MODE ANALYSIS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN
LOSS OF COOLANT
M CODES
PIPES
PRESTRESSED CONCRETE
PUMPS
REACTOR CORE DISRUPTION
US NRC
ACCIDENTS
BUILDING MATERIALS
COMPOSITE MATERIALS
CONCRETES
CONTAINMENT
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
MATERIALS
NATIONAL ORGANIZATIONS
NONMETALS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TURKEY POINT-3 REACTOR
RISK ASSESSMENT
TURKEY POINT-4 REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
DAMAGE
DRAINAGE
ECCS
FAILURE MODE ANALYSIS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN
LOSS OF COOLANT
M CODES
PIPES
PRESTRESSED CONCRETE
PUMPS
REACTOR CORE DISRUPTION
US NRC
ACCIDENTS
BUILDING MATERIALS
COMPOSITE MATERIALS
CONCRETES
CONTAINMENT
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
MATERIALS
NATIONAL ORGANIZATIONS
NONMETALS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled