1-11 of 11
Risk
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Overview of NRC NUREG-1482, Revision 3, Guidelines for Inservice Testing at Nuclear Power Plants – Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restrains (Snubbers) at Nuclear Power Plants

Gurjendra S. Bedi
Proc. ASME. NRC2022, ASME/NRC 2022 14th OM Code Symposium, V001T04A001, January 19–20, 2022
Publisher: American Society of Mechanical Engineers
Paper No: NRC2022-63153
https://doi.org/10.1115/NRC2022-63153
View Paper titled, Overview of NRC NUREG-1482, Revision 3, Guidelines for Inservice Testing at Nuclear Power Plants – Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restrains (Snubbers) at Nuclear Power Plants
Open the PDF for Overview of NRC NUREG-1482, Revision 3, Guidelines for Inservice Testing at Nuclear Power Plants – Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restrains (Snubbers) at Nuclear Power Plants in another window
Topics: In-service testing, Nuclear power stations, Pumps, Testing, Valves, In-service inspection, Mechanical engineers, Nuclear power plant maintenance, Risk, Service life (Equipment)
Proceedings Papers

NRC Inspection Manual Inspection Procedure 71111 Attachment 21N.02: Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection Implementation Update and Lessons Learned

Douglas Bollock
Proc. ASME. NRC2022, ASME/NRC 2022 14th OM Code Symposium, V001T07A002, January 19–20, 2022
Publisher: American Society of Mechanical Engineers
Paper No: NRC2022-76952
https://doi.org/10.1115/NRC2022-76952
View Paper titled, NRC Inspection Manual Inspection Procedure 71111 Attachment 21N.02: Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection Implementation Update and Lessons Learned
Open the PDF for NRC Inspection Manual Inspection Procedure 71111 Attachment 21N.02: Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection Implementation Update and Lessons Learned in another window
Topics: Design, Inspection, Valves, Nuclear power stations, Engineering standards, Feedback, Licensing, Regulations, Reliability, Risk
Proceedings Papers

Regulatory Perspectives on ASME OM Code, Mandatory Appendix IV, Revision 0, “Inservice Testing of Air-Operated Valves in Light-Water Reactor Nuclear Power Plants”

Jason Carneal
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 107-121, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5002
https://doi.org/10.1115/NRC2014-5002
View Paper titled, Regulatory Perspectives on ASME OM Code, Mandatory Appendix IV, Revision 0, “Inservice Testing of Air-Operated Valves in Light-Water Reactor Nuclear Power Plants”
Open the PDF for Regulatory Perspectives on ASME OM Code, Mandatory Appendix IV, Revision 0, “Inservice Testing of Air-Operated Valves in Light-Water Reactor Nuclear Power Plants” in another window
Topics: In-service testing, Light water reactors, Nuclear power stations, Valves, Testing, Design, Mechanical engineers, Nuclear power plant maintenance, Regulations, Risk
Proceedings Papers

Regulatory Perspectives on Risk-Informed Inservice Testing

John Billerbeck
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 131-137, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5022
https://doi.org/10.1115/NRC2014-5022
View Paper titled, Regulatory Perspectives on Risk-Informed Inservice Testing
Open the PDF for Regulatory Perspectives on Risk-Informed Inservice Testing in another window
Topics: In-service testing, Risk
Proceedings Papers

OM Code Activities for New Reactors

Ronald Lippy
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 316-324, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5012
https://doi.org/10.1115/NRC2014-5012
View Paper titled, OM Code Activities for New Reactors
Open the PDF for OM Code Activities for New Reactors in another window
Topics: Accidents, Construction, Cycles, Heat, In-service testing, Licensing, Light water reactors, Mechanical engineers, Nuclear power plant maintenance, Nuclear power stations
Proceedings Papers

Inservice Testing for Small Modular Nuclear Reactor Plants

Gary P. McGee, Steven M. Unikewicz
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T07A001, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3506
https://doi.org/10.1115/PVS2017-3506
View Paper titled, Inservice Testing for Small Modular Nuclear Reactor Plants
Open the PDF for Inservice Testing for Small Modular Nuclear Reactor Plants in another window
Topics: In-service testing, Nuclear reactors, Testing, Construction, Nuclear power stations, Reactor vessels, Small modular reactors, Valves, Boilers, Containment vessels
Proceedings Papers

Risk-Informed In-Service Testing Programs

Bradley J. Scott
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T06A001, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3527
https://doi.org/10.1115/PVS2017-3527
View Paper titled, Risk-Informed In-Service Testing Programs
Open the PDF for Risk-Informed In-Service Testing Programs in another window
Topics: In-service testing, Risk, Testing, Pumps, Valves, Safety
Proceedings Papers

What Is Your Actual Pump Flow Rate?

Norman F. Perkins, Philip S. Stacy
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T02A003, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3512
https://doi.org/10.1115/PVS2017-3512
View Paper titled, What Is Your Actual Pump Flow Rate?
Open the PDF for What Is Your Actual Pump Flow Rate? in another window
Topics: Flow (Dynamics), Pumps, Testing, Testing performance, Power stations, Uncertainty, Biomass, Condensers (steam plant), Engineering standards, Flow measurement
Proceedings Papers

ASME OM Code Implementation Lessons Learned for the AP1000 ® Plant

Augustine A. Cardillo, Natalie M. Rodgers
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T07A003, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3546
https://doi.org/10.1115/PVS2017-3546
View Paper titled, ASME OM Code Implementation Lessons Learned for the AP1000 ® Plant
Open the PDF for ASME OM Code Implementation Lessons Learned for the AP1000 ® Plant in another window
Topics: Design, In-service testing, Mechanical engineers, Nuclear power plant maintenance, Plant design, Regulations, Risk, Safety, Testing
Proceedings Papers

Predictive Monitoring of Main Steam Safety Valves

Jessica Patrone, Phillip Twaddle
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T04A003, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3539
https://doi.org/10.1115/PVS2017-3539
View Paper titled, Predictive Monitoring of Main Steam Safety Valves
Open the PDF for Predictive Monitoring of Main Steam Safety Valves in another window
Topics: Safety, Steam, Valves, Maintenance, Disks, Flanges, Leakage, Power stations, Risk, Systems engineers
Proceedings Papers

ASME OM Code Subsection ISTE: A Discussion of the Upcoming Subsection

Craig D. Sellers
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T06A003, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3545
https://doi.org/10.1115/PVS2017-3545
View Paper titled, ASME OM Code Subsection ISTE: A Discussion of the Upcoming Subsection
Open the PDF for ASME OM Code Subsection ISTE: A Discussion of the Upcoming Subsection in another window
Topics: In-service testing, Pumps, Risk, Safety, Testing, Valves