Ultrasonic inspection reliability for intergranular stress corrosion cracks

Technical Report · Sun Jul 01 04:00:00 EDT 1990

DOI:https://doi.org/10.2172/6888871· OSTI ID:6888871

Heasler, P G; Taylor, T T; Spanner, J C; Doctor, S R; Deffenbaugh, J D ^[1]

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1. Pacific Northwest Lab., Richland, WA (USA)

A pipe inspection round robin entitled Mini-Round Robin'' was conducted at Pacific Northwest Laboratory from May 1985 through October 1985. The research was sponsored by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under a program entitled Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors.'' The Mini-Round Robin (MRR) measured the intergranular stress corrosion (GSC) crack detection and sizing capabilities of inservice inspection (ISI) inspectors that had passed the requirements of IEB 83-02 and the Electric Power Research Institute (EPRI) sizing training course. The MRR data base was compared with an earlier Pipe Inspection Round Robin (PIRR) that had measured the performance of inservice inspection prior to 1982. Comparison of the MRR and PIRR data bases indicates no significant change in the inspection capability for detecting IGSCC. Also, when comparing detection of long and short cracks, no difference in detection capability was measured. An improvement in the ability to differentiate between shallow and deeper IGSCC was found when the MRR sizing capability was compared with an earlier sizing round robin conducted by the EPRI. In addition to the pipe inspection round robin, a human factors study was conducted in conjunction with the Mini-Round Robin. The most important result of the human factors study is that the Relative Operating Characteristics (ROC) curves provide a better methodology for describing inspector performance than only probability of detection (POD) or single-point crack/no crack data. 6 refs., 55 figs., 18 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6888871
• Report Number(s): NUREG/CR-4908; PNL-6196; ON: TI90016320
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ACOUSTIC TESTING
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CORROSION
CRACKS
DATA
EXPERIMENTAL DATA
HIGH ALLOY STEELS
HUMAN FACTORS
IN-SERVICE INSPECTION
INFORMATION
INSPECTION
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PERSONNEL
PIPES
POWER PLANTS
REACTOR OPERATORS
RECOMMENDATIONS
RELIABILITY
STAINLESS STEELS
STANDARDS
STEELS
STRESS CORROSION
SURVEYS
TESTING
THERMAL POWER PLANTS
TRAINING
ULTRASONIC TESTING