Guidelines for Evaluation of Non-Safety Class 1 Structural Components Having Effects on Safety Class 1 Equipment

Conference · Fri Mar 01 04:00:00 EST 1991

OSTI ID:5787566

LaSalle, F. R. ^[1]; Golberg, P. R. ^[1]; Mackey, T. C. ^[1]

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1. Westinghouse Hanford Co., Richland, WA (United States)

Non-Safety Class 1 piping, vessels, and equipment require substantial seismic evaluation to ensure that failure during an earthquake does not result in Safety Class 1 equipment pressure boundary failure, distortion, or loss of function. Design analysis guidelines for non-Safety Class 1 equipment are presented that address applied loads, seismic inertia loads, and damping values. Approaches to evaluating existing equipment anchorage, anchor bolt allowables, piping contributory masses for support evaluation, and proposed allowable stresses are discussed. Proposed allowables are developed for piping, electrical conduit, and heating and ventilation ducting. Applications of the guidelines to nuclear reactor and nuclear facilities are discussed.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 5787566
• Report Number(s): WHC-SA--1156; CONF-910602--41; ON: DE91012199
• Country of Publication: United States
• Language: English

Related Subjects

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22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
58 GEOSCIENCES
580000 -- Geosciences
BUILDINGS
CONTAINERS
DAMPING
DUCTS
DYNAMIC LOADS
EARTHQUAKES
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ENGINEERING
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FASTENERS
FFTF REACTOR
GRAPHITE MODERATED REACTORS
HANFORD PRODUCTION REACTORS
HANFORD RESERVATION
JOINTS
LIQUID METAL COOLED REACTORS
LWGR TYPE REACTORS
MECHANICAL VIBRATIONS
N-REACTOR
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PIPES
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY ANALYSIS
SAFETY ENGINEERING
SEISMIC EFFECTS
SEISMIC EVENTS
SHEAR
SODIUM COOLED REACTORS
STRESSES
SYSTEMS ANALYSIS
TEST REACTORS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS