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Proceedings Papers

Proceedings Volume Cover
ASME/NRC 2022 14th OM Code Symposium
January 19–20, 2022
Virtual, Online
Conference Sponsors:
  • ASME
ISBN:
978-0-7918-8570-3
ASME/NRC 2022 14th OM Code Symposium

Front Matter

NRC2022 Front Matter
PVS 2022; V001T00A001doi:https://doi.org/10.1115/NRC2022-FM1
View Articletitled, NRC2022 Front Matter
PDF

OM Scope / General Requirement

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
PVS 2022; V001T04A001doi:https://doi.org/10.1115/NRC2022-63153
View Articletitled, 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
PDF
Topics: In-service testing , Nuclear power stations , Pumps , Testing , Valves , In-service inspection , Mechanical engineers , Nuclear power plant maintenance , Risk , Service life (Equipment)
Augmented IST Program Requirements – Scope and Testing
Mark Gowin
PVS 2022; V001T04A002doi:https://doi.org/10.1115/NRC2022-77128
View Articletitled, Augmented IST Program Requirements – Scope and Testing
PDF
Topics: ASME Standards , Safety , Testing

Pumps

Condition Monitoring for Pumps
Wavel Justice, Thomas Ruggiero
PVS 2022; V001T05A001doi:https://doi.org/10.1115/NRC2022-63143
View Articletitled, Condition Monitoring for Pumps
PDF
Topics: Condition monitoring , Pumps , Engines , Motors , Valves , Testing , Electrical components , Electronic systems , Emission spectroscopy , Nuclear power stations
Operationally Focused Management of Pumps in Alert: Using Analysis to Remove a High Pressure Safety Injection Pump From Increased-Frequency Test Schedule
Eli Arnold
PVS 2022; V001T05A002doi:https://doi.org/10.1115/NRC2022-63146
View Articletitled, Operationally Focused Management of Pumps in Alert: Using Analysis to Remove a High Pressure Safety Injection Pump From Increased-Frequency Test Schedule
PDF
Topics: High pressure (Physics) , Pumps , Safety
Pump Performance Requirements, Test Margins, and the Impact of Emergency Diesel Generator Voltage and Frequency Tolerances
Thomas G. Loebig, Stephen R. Swantner
PVS 2022; V001T05A003doi:https://doi.org/10.1115/NRC2022-63150
View Articletitled, Pump Performance Requirements, Test Margins, and the Impact of Emergency Diesel Generator Voltage and Frequency Tolerances
PDF
Topics: Acceptance criteria , Design , Diesel generators , Emergencies , In-service testing , Pumps
ASME OM ISTB Code Vibration Changes: Vibration Calibration Frequency Response Range and Wording Changes
Edward Hudson, David Anderson, Nick Camilli
PVS 2022; V001T05A004doi:https://doi.org/10.1115/NRC2022-76987
View Articletitled, ASME OM ISTB Code Vibration Changes: Vibration Calibration Frequency Response Range and Wording Changes
PDF
Topics: Calibration , Frequency response , Vibration , Instrumentation , Data collection , Electricity (Physics) , In-service testing , Maintenance , Nuclear power stations , Pumps

Snubbers

Results of Mechanical Snubber Condition Monitoring on Degradation Rate Over Time
Mark Shutt
PVS 2022; V001T06A001doi:https://doi.org/10.1115/NRC2022-63141
View Articletitled, Results of Mechanical Snubber Condition Monitoring on Degradation Rate Over Time
PDF
Topics: Condition monitoring , Reliability , Service life (Equipment) , Nuclear power stations

Valves

Optimized Compliance With Supplemental Indication Requirements: Leveraging Non-Intrusive Techniques, Preexisting Line-Ups and Programs to Meet 10CFR50.55a(b)(3)(xi)
Eli Arnold, Domingo Cruz
PVS 2022; V001T07A001doi:https://doi.org/10.1115/NRC2022-63151
View Articletitled, Optimized Compliance With Supplemental Indication Requirements: Leveraging Non-Intrusive Techniques, Preexisting Line-Ups and Programs to Meet 10CFR50.55a(b)(3)(xi)
PDF
Topics: Disks , Nuclear power stations , Power stations , Pressurized water reactors , Testing , Ultrasonic testing equipment , Valves
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
PVS 2022; V001T07A002doi:https://doi.org/10.1115/NRC2022-76952
View Articletitled, 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
PDF
Topics: Design , Inspection , Valves , Nuclear power stations , Engineering standards , Feedback , Licensing , Regulations , Reliability , Risk
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