Feasibility of developing generic piping inservice inspection requirements
- Pacific Northwest Lab., Richland, WA (USA)
The objectives of a multiyear program entitled Nondestructive Evaluation Reliability for In-Service Inspection of Light Water Reactors (LWRs), which is being conducted at Pacific Northwest Laboratory (PNL), are to determine the reliability of current in-service inspections (ISI) of pressure boundary systems and components and to develop recommendations that can ensure a suitably high inspection reliability. The long-term objective is to propose changes to Sec. XI of the American Society of mechanical Engineers' code for inspection of nuclear power plant components. In evaluating methods that could be used to provide a technical basis for improved ISI plans, PNL developed a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. The feasibility of generic ISI requirements is being evaluated in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. In this phase, PNL establishes the extent to which generic insights drawn from detailed evaluations of selected plants can be extrapolated to different classes of LWRs. This paper presents phase-I results of evaluations for eight selected plant PRAs. The results of these evaluations will be consolidated into requirements for comprehensive piping system inspections that will be developed in phase II.
- OSTI ID:
- 6434416
- Report Number(s):
- CONF-891103-; CODEN: TANSA; TRN: 90-035234
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (USA), 26-30 Nov 1989; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Feasibility of developing generic piping inservice inspection requirements
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ENGINEERED SAFETY SYSTEMS
PRIMARY COOLANT CIRCUITS
REACTOR SAFETY
IN-SERVICE INSPECTION
PWR TYPE REACTORS
BATTELLE PACIFIC NORTHWEST LABORATORIES
FAILURES
FEASIBILITY STUDIES
HIGH PRESSURE COOLANT INJECTION
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
NONDESTRUCTIVE TESTING
PIPES
PROBABILITY
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
RISK ASSESSMENT
RUPTURES
WELDED JOINTS
ACCIDENTS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
INSPECTION
JOINTS
MATERIALS TESTING
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
TESTING
US DOE
US ERDA
US ORGANIZATIONS
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WATER MODERATED REACTORS
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