Seismic verification of nuclear plant equipment anchorage, Revision 1

Technical Report · Sat Jun 01 04:00:00 EDT 1991

OSTI ID:5189804

Czarnecki, R M ^[1]

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1. URS/John A. Blume and Associates, Engineers, San Francisco, CA (United States)

Guidelines have been developed to evaluate the seismic adequacy of the anchorage of various classes of electrical and mechanical equipment in nuclear power plants covered by NRC Unresolved Safety Issue A-46. The guidelines consist of anchorage strength capacities as a function of key equipment and installation parameters. The strength criteria for expansion anchor bolts were developed by collecting and analyzing a large quantity of test data. The strength criteria for Cast-in-Place bolts and welds to embedded steel plates and channels were taken from existing nuclear-industry design guidelines. For anchorage used in low strength concrete and in concrete with cracks, appropriate strength reduction factors were developed. Reduction factors for parameters such as edge distance, spacing and embedment depth are also included. Based on the anchorage capacity and equipment configuration, inspection checklists for field verification of anchorage adequacy were developed, and provisions for outliners that can be used to further investigate anchorages that cannot be verified in the field were prepared. The screening tables are based on an analysis of the anchorage forces developed by common equipment types and on strength criteria to quantify the holding power of anchor bolts and welds. A computer code EBAC was developed for the evaluation of the adequacy of the equipment anchorage. Guidelines to evaluate anchorage adequacy for vertical and horizontal tanks and horizontal heat exchangers were also developed.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); URS/John A. Blume and Associates, Engineers, San Francisco, CA (United States)
• Sponsoring Organization: EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 5189804
• Report Number(s): EPRI-NP-5228-M-Rev.1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANCHORS
COMPUTER CODES
CONTAINERS
E CODES
EARTHQUAKES
ELECTRICAL EQUIPMENT
EQUIPMENT
FASTENERS
HEAT EXCHANGERS
INSPECTION
JOINTS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
SAFETY
SEISMIC EFFECTS
SEISMIC EVENTS
STANDARDS
TANKS
THERMAL POWER PLANTS
WELDED JOINTS