A methodology for assessment of nuclear power plant seismic margin

Technical Report · Thu Aug 01 04:00:00 EDT 1991

OSTI ID:5371976

Reed, J W ^[1]; Kennedy, R P ^[2]; Buttemer, D R ^[3]; Idriss, I M ^[4]; Moore, D P; Barr, T; Wooten, K D; Smith, J E ^[5]

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1. Benjamin (J.R.) and Associates, Inc., Mountain View, CA (United States)
2. Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States)
3. Pickard, Lowe and Garrick, Inc., Newport Beach, CA (United States)
4. California Univ., Davis, CA (United States). Dept. of Civil Engineering
5. South

EPRI's seismic margin methodology enables utility engineers to quantify a nuclear power plant's ability to withstand an earthquake greater than design and still safety shut down for a least 72 hours. This cost-effective, practical methodology used generic screening of systems and component seismic reggedness and does not require probabilistic calculations. The revision adds depth, detail, and more complete procedures to the original report but does not change the basic method. The seismic margin methodology enables engineers to choose a functional success path and several alternatives to shut down the plant and to identify the subset of plant structures and components associated with the path selected. The methodology further provides guidelines for screening the seismic ruggedness of subset components and structures. Components that satisfy screening criteria require no further evaluation. Remaining components require deterministic evaluations using in-structure motions calculated for the earthquake being assessed. The seismic margin earthquake (SME) is chosen to be sufficiently larger than the SSE to establish a significant seismic margin. Methodology procedures determine the weakest link components and establish the HCLPF level of ground moton for which the plant can safely shut down. Plant walkdowns ensure component compliance with screening guideline conditions. The revision gives detailed methods for calculating HCLPF values for an extensive variety of components.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Benjamin (J.R.) and Associates, Inc., Mountain View, CA (United States); Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States); Pickard, Lowe and Garrick, Inc., Newport Beach, CA (United States); California Univ., Davis, CA (United States). Dept. of Civil Engineering; Southern Co. Services, Inc., Birmingham, AL (United States)
• Sponsoring Organization: EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 5371976
• Report Number(s): EPRI-NP-6041-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
CONTROL EQUIPMENT
COOLING SYSTEMS
DYNAMIC LOADS
EARTHQUAKES
ELECTRICAL EQUIPMENT
ENERGY SYSTEMS
ENGINEERING
EQUIPMENT
FLOW REGULATORS
FUNCTIONS
GROUND MOTION
LIMITING VALUES
MECHANICAL STRUCTURES
MOTION
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
RESPONSE FUNCTIONS
RISK ASSESSMENT
SEISMIC EFFECTS
SEISMIC EVENTS
SHUTDOWN
SOIL-STRUCTURE INTERACTIONS
THERMAL POWER PLANTS
VALVES