Steam generator group project: Task 13 final report: Nondestructive examination validation
The Steam Generator Group Project (SGGP) was a multi-task effort using the retired-from-service Surry 2A pressurized water reactor steam generator as a test bed to investigate the reliability and effectiveness of in-service nondestructive eddy current (EC) inspection equipment and procedures. The information developed provided the technical basis for recommendations for improved in- service inspection and tube plugging criteria of steam generators. This report describes the results and analysis from Task 13--NDE Validation. The primary objective of Task 13 was to validate the EC inspection to detect and size tube defects. Additional objectives were to assess the nature and severity of tube degradation from all regions of the generator and to measure the remaining integrity of degraded specimens by burst testing. More than 550 specimens were removed from the generator and included in the validation studies. The bases for selecting the specimens and the methods and procedures used for specimen removal from the generator are reported. Results from metallurgical examinations of these specimens are presented and discussed. These examinations include visual inspection of all specimens to locate and identify tube degradation, metallographic examination of selected specimens to establish defect severity and burst testing of selected specimens to establish the remaining integrity of service-degraded tubes. Statistical analysis of the combined metallurgical and EC data to determine the probability of detection (POD) and sizing accuracy are reported along with a discussion of the factors which influenced the EC results. Finally, listings of the metallurgical and corresponding EC data bases are given. 12 refs., 141 figs., 24 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6815145
- Report Number(s):
- NUREG/CR-5185; PNL-6399; ON: TI89001449
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PWR TYPE REACTORS
STEAM GENERATORS
EDDY CURRENT TESTING
COMPILED DATA
DEFECTS
IN-SERVICE INSPECTION
METALLURGICAL EFFECTS
PROGRESS REPORT
STATISTICAL DATA
STATISTICS
STRESS CORROSION
SURRY-2 REACTOR
TUBES
BOILERS
CHEMICAL REACTIONS
CORROSION
DATA
DOCUMENT TYPES
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
INFORMATION
INSPECTION
MATERIALS TESTING
MATHEMATICS
NONDESTRUCTIVE TESTING
NUMERICAL DATA
POWER REACTORS
REACTORS
TESTING
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled