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Proceedings Papers

Pump Performance Requirements, Test Margins, and the Impact of Emergency Diesel Generator Voltage and Frequency Tolerances

Thomas G. Loebig, Stephen R. Swantner
Proc. ASME. NRC2022, ASME/NRC 2022 14th OM Code Symposium, V001T05A003, January 19–20, 2022
Publisher: American Society of Mechanical Engineers
Paper No: NRC2022-63150
https://doi.org/10.1115/NRC2022-63150
View Paper titled, Pump Performance Requirements, Test Margins, and the Impact of Emergency Diesel Generator Voltage and Frequency Tolerances
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Topics: Acceptance criteria, Design, Diesel generators, Emergencies, In-service testing, Pumps
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
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Topics: Design, Inspection, Valves, Nuclear power stations, Engineering standards, Feedback, Licensing, Regulations, Reliability, Risk
Proceedings Papers

AOV Quarter-Turn Efficiency Models and Validation

Zachary Leutwyler, Emil Leutwyler, Neal Estep
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 192-207, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5031
https://doi.org/10.1115/NRC2014-5031
View Paper titled, AOV Quarter-Turn Efficiency Models and Validation
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Topics: Actuators, Bearings, Bronze, Design, Diaphragms (Mechanical devices), Diaphragms (Structural), Friction, Levers, Needles, Nuclear power stations
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”
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Topics: In-service testing, Light water reactors, Nuclear power stations, Valves, Testing, Design, Mechanical engineers, Nuclear power plant maintenance, Regulations, Risk
Proceedings Papers

Effective Diaphragm Area Test Program for Air-Operated Valve Actuators

Zachary Leutwyler, Lisa Thidavanh, Neal Estep
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 181-191, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5028
https://doi.org/10.1115/NRC2014-5028
View Paper titled, Effective Diaphragm Area Test Program for Air-Operated Valve Actuators
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Topics: Diaphragms (Mechanical devices), Diaphragms (Structural), Valve actuators, Actuators, Testing, Pressure, Springs, Design, Manufacturing, Measurement uncertainty
Proceedings Papers

Design and Test for a High-Temperature Molten Salt Pump

Zhong Li, Yuan Fu, Jianyu Zhang, Liancheng Lin, Jianping Huang, Wenyu Mao, Dongsheng Yang, Dandan Zhao, Xiao Wang
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 208-222, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5024
https://doi.org/10.1115/NRC2014-5024
View Paper titled, Design and Test for a High-Temperature Molten Salt Pump
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Topics: Design, High temperature, Pumps, Temperature, Hydraulics, Bearings, Flow (Dynamics), Thermal stresses, Corrosion resistance, Engines
Proceedings Papers

Preliminary Study of the Use of Freeze-Valves for a Passive Shutdown System in Molten Salt Reactors

Qiming Li, Zhongfeng Tang, Yuan Fu, Zhong Li, Naxiu Wang
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 325-341, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5025
https://doi.org/10.1115/NRC2014-5025
View Paper titled, Preliminary Study of the Use of Freeze-Valves for a Passive Shutdown System in Molten Salt Reactors
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Topics: Molten salt reactors, Valves, Design, Accidents, Chain, Control systems, Finite element methods, Fuels, Generation IV reactors, Graphite
Proceedings Papers

IST Management Software for Check Valves, MOVs, and AOVs

Neal Estep, Ryan Sicking
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 279-294, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5027
https://doi.org/10.1115/NRC2014-5027
View Paper titled, IST Management Software for Check Valves, MOVs, and AOVs
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Topics: Computer software, Valves, Design, In-service testing, Condition monitoring, Databases, Engineers, Engines, Feedback, Inspection
Proceedings Papers

Qualification of Pumps and Valves for the Safety Injection Path of Nuclear Power Plants

Ingo Ganzmann, Holger Schmidt
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 356-373, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5040
https://doi.org/10.1115/NRC2014-5040
View Paper titled, Qualification of Pumps and Valves for the Safety Injection Path of Nuclear Power Plants
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Topics: Nuclear power stations, Pumps, Safety, Valves, Construction, Design, Inspection, Insulation, International Organization for Standardization, Maintenance
Proceedings Papers

Inservice Testing Program Improvements for New Reactors: Small Modular Reactors

Ronald Lippy
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 342-355, June 23–25, 2014
Publisher: American Society of Mechanical Engineers
Paper No: NRC2014-5032
https://doi.org/10.1115/NRC2014-5032
View Paper titled, Inservice Testing Program Improvements for New Reactors: Small Modular Reactors
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Topics: In-service testing, Small modular reactors, Construction, Licensing, Nuclear power stations, Pumps, Testing, Valves, Design, Inspection
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
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Topics: In-service testing, Nuclear reactors, Testing, Construction, Nuclear power stations, Reactor vessels, Small modular reactors, Valves, Boilers, Containment vessels
Proceedings Papers

Implementation of ASME OM Requirements in IST Programs in Spain: Special Focus on ISTA General Requirements

Francisco Fiol Martínez, Jesús García Rocasolano
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T01A001, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3505
https://doi.org/10.1115/PVS2017-3505
View Paper titled, Implementation of ASME OM Requirements in IST Programs in Spain: Special Focus on ISTA General Requirements
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Topics: Design, Engineering standards, In-service inspection, Nuclear power stations, Probability, Regulations, Risk assessment, Safety
Proceedings Papers

Curtiss-Wright Advanced NozzleCheck Valves for Generation III+ Nuclear Power Plants

Haykaz Mkrtchyan, Ararat Torosyan, Tsolag Apelian
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T07A002, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3511
https://doi.org/10.1115/PVS2017-3511
View Paper titled, Curtiss-Wright Advanced NozzleCheck Valves for Generation III+ Nuclear Power Plants
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Topics: Nuclear power stations, Valves, Flow (Dynamics), Design, Computational fluid dynamics, Bushings, Damage, Engineering prototypes, Fluids, Gates (Closures)
Proceedings Papers

Evaluating AOV and MOV Performance

Tom Walker, Nick Camilli
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T03A001, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3503
https://doi.org/10.1115/PVS2017-3503
View Paper titled, Evaluating AOV and MOV Performance
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Topics: Actuators, Design, Disks, Friction, Gates (Closures), Stress, Thrust, Valves
Proceedings Papers

Plant Performance History of an Innovative Gate Valve in Critical Service Applications

M. S. Kalsi, Patricio Alvarez, Thomas White, Micheal Green
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T04A002, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3536
https://doi.org/10.1115/PVS2017-3536
View Paper titled, Plant Performance History of an Innovative Gate Valve in Critical Service Applications
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Topics: Gates (Closures), Valves, Design, Boiling water reactors, Leakage, Maintenance, Nuclear power stations, Pipes, Pressurized water reactors, Rupture
Proceedings Papers

Estimating Safety Valve Stochastic Failure-to-Close Probabilities for the Purpose of Nuclear Reactor Severe Accident Analysis

S. Tina Ghosh, Alfred Hathaway, III, Hossein Esmaili, Kyle W. Ross, Douglas M. Osborn, Kenneth C. Wagner
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T06A002, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3538
https://doi.org/10.1115/PVS2017-3538
View Paper titled, Estimating Safety Valve Stochastic Failure-to-Close Probabilities for the Purpose of Nuclear Reactor Severe Accident Analysis
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Topics: Accidents, Failure, Nuclear reactors, Probability, Safety, Valves, Pressurized water reactors, Testing, Pressure, Containment
Proceedings Papers

Expectations for Inservice Testing Programs at New Nuclear Power Plants

Thomas G. Scarbrough
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T01A005, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3535
https://doi.org/10.1115/PVS2017-3535
View Paper titled, Expectations for Inservice Testing Programs at New Nuclear Power Plants
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Topics: In-service testing, Nuclear power stations, Valves, Licensing, Pumps, Regulations, Safety, Testing, Acceptance criteria, ASME Standards
Proceedings Papers

Terry Turbopump Expanded Operating Band

Douglas M. Osborn, Kyle Ross, Jeff Cardoni, Matt Solom, Haihua Zhao, James O’Brien, Karen Vierow-Kirkland, Mark Bergman, Randy Bunt
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T01A002, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3508
https://doi.org/10.1115/PVS2017-3508
View Paper titled, Terry Turbopump Expanded Operating Band
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Topics: Accidents, Batteries, Boiling water reactors, Coolants, Cooling systems, Design, Failure, Feedwater, Floods, Fukushima nuclear disaster, Japan, 2011
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
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Topics: Design, In-service testing, Mechanical engineers, Nuclear power plant maintenance, Plant design, Regulations, Risk, Safety, Testing
Proceedings Papers

Design Basis Verification and Preservice Testing Considerations for OM Code Mandatory Appendix III

Neal E. Estep
Proc. ASME. PVS2017, ASME/NRC 2017 13th Pump and Valve Symposium, V001T03A002, July 17–18, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVS2017-3504
https://doi.org/10.1115/PVS2017-3504
View Paper titled, Design Basis Verification and Preservice Testing Considerations for OM Code Mandatory Appendix III
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Topics: Design, Testing, In-service testing, Valves, Maintenance, Bridges (Structures), Engines, Motors