Basis for snubber aging research: Nuclear Plant Aging Research Program

Technical Report · Sun Dec 31 23:00:00 EST 1989

DOI:https://doi.org/10.2172/5065261· OSTI ID:5065261

Brown, D. P. ^[1]; Palmer, G. R. ^[2]; Werry, E. V.; Blahnik, D. E. ^[3]

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1. Lake Engineering Co., Greenville, RI (USA)
2. Wyle Labs., Huntsville, AL (USA)
3. Pacific Northwest Lab., Richland, WA (USA)

This report describes a research plan to address the safety concerns of aging in snubbers used on piping and equipment in commercial nuclear power plants. The work is to be performed under Phase 2 of the Snubber Aging Study of the Nuclear Plant Aging Research Program of the US Nuclear Regulatory Commission with the Pacific Northwest Laboratory (PNL) as the prime contractor. Research conducted by PNL under Phase 1 provided an initial assessment of snubber operating experience and was primarily based on a review of licensee event reports. The work proposed is an extension of Phase 1 and includes research at nuclear power plants and in test laboratories. Included is technical background on the design and use of snubbers in commercial nuclear power applications; the primary failure modes of both hydraulic and mechanical snubbers are discussed. The anticipated safety, technical, and regulatory benefits of the work, along with concerns of the NRC and the utilities, are also described. 21 refs., 7 figs., 1 tab.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Lake Engineering Co., Greenville, RI (USA); Wyle Labs., Huntsville, AL (USA); Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5065261
• Report Number(s): NUREG/CR-5386; PNL--6911; ON: TI90006658
• 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
AGING
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
FAILURE MODE ANALYSIS
FORECASTING
FRACTURE MECHANICS
IN-SITU PROCESSING
INSPECTION
MEASURING METHODS
MECHANICAL STRUCTURES
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE EFFECTS
PROCESSING
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESTRAINTS
RISK ASSESSMENT
SAFETY
SEALS
SEISMIC EFFECTS
SERVICE LIFE
SUPPORTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TECHNOLOGY ASSESSMENT
TEMPERATURE EFFECTS
THERMAL POWER PLANTS