Seismic margin review of the Maine Yankee Atomic Power Station: Systems analysis
Technical Report
·
OSTI ID:6614043
The overall objectives of this review are to assess the seismic margins of the Maine Yankee pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.
- Research Organization:
- Energy, Inc., Kent, WA (USA); Lawrence Livermore National Lab., CA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering Safety
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6614043
- Report Number(s):
- NUREG/CR-4826; UCID-20948-Vol.2; ON: TI87007801
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
COOLING SYSTEMS
DOCUMENT TYPES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
LOSS OF COOLANT
MAINE YANKEE REACTOR
MECHANICS
OPERATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
REVIEWS
RHR SYSTEMS
SAFETY
SEISMIC EFFECTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
COOLING SYSTEMS
DOCUMENT TYPES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
LOSS OF COOLANT
MAINE YANKEE REACTOR
MECHANICS
OPERATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
REVIEWS
RHR SYSTEMS
SAFETY
SEISMIC EFFECTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS