Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection
Abstract
The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show thatmore »
- Authors:
- Publication Date:
- Research Org.:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Org.:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI Identifier:
- 10178637
- Report Number(s):
- NUREG/CR-6151; PNL-8912
ON: TI94018068; TRN: 94:016748
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: Aug 1994
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; WATER COOLED REACTORS; IN-SERVICE INSPECTION; REACTOR COMPONENTS; NONDESTRUCTIVE TESTING; FEASIBILITY STUDIES; RISK ASSESSMENT; 210100; 210200; 220900; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; REACTOR SAFETY
Citation Formats
Vo, T V, Smith, B W, Simonen, F A, and Gore, B F. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection. United States: N. p., 1994.
Web. doi:10.2172/10178637.
Vo, T V, Smith, B W, Simonen, F A, & Gore, B F. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection. United States. https://doi.org/10.2172/10178637
Vo, T V, Smith, B W, Simonen, F A, and Gore, B F. 1994.
"Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection". United States. https://doi.org/10.2172/10178637. https://www.osti.gov/servlets/purl/10178637.
@article{osti_10178637,
title = {Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection},
author = {Vo, T V and Smith, B W and Simonen, F A and Gore, B F},
abstractNote = {The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors.},
doi = {10.2172/10178637},
url = {https://www.osti.gov/biblio/10178637},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Aug 01 00:00:00 EDT 1994},
month = {Mon Aug 01 00:00:00 EDT 1994}
}