Nondestructive examination (NDE) reliability for inservice inspection of light water reactors

Technical Report · Sun Oct 01 00:00:00 EDT 1989

OSTI ID:5230025

Doctor, S R; Deffenbaugh, J D; Good, M S; Green, E R; Heasler, P G; Simonen, F A; Spanner, J C; Taylor, T T ^[1]

---

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

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvement that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements based on material properties, service conditions, and NDE capabilities and uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from October 1987 through March 1988. 21 refs., 28 figs., 2 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5230025
• Report Number(s): NUREG/CR-4469-Vol.8; PNL-5711-Vol.8; ON: TI90005362; TRN: 90-004328
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
INSPECTION
RELIABILITY
PWR TYPE REACTORS
COMPLIANCE
DATA COVARIANCES
DESIGN
FAILURE MODE ANALYSIS
FRACTURE MECHANICS
MEASURING METHODS
PIPES
PLANNING
PRESSURE VESSELS
PROBABILISTIC ESTIMATION
PROGRAM MANAGEMENT
PROGRESS REPORT
REACTOR TECHNOLOGY
RECOMMENDATIONS
REGULATIONS
RISK ASSESSMENT
STAINLESS STEELS
TASK SCHEDULING
ALLOYS
CONTAINERS
DATA PROCESSING
DOCUMENT TYPES
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MECHANICS
PROCESSING
REACTORS
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled