Skip to Main Content
American Society of Mechanical Engineers: Digital Collection
Cart
header search
Search
Advanced Search
Skip Nav Destination

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; V001T00A001https://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; V001T04A001https://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; V001T04A002https://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; V001T05A001https://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; V001T05A002https://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; V001T05A003https://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; V001T05A004https://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; V001T06A001https://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; V001T07A001https://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; V001T07A002https://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
All Years

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

  • Crossref Logo
  • Crossref Open Funder Registry Logo
  • Crossref Open Cited-By Logo
  • Crossref Crossmark Logo
  • Crossref Similarity Check Logo
  • Chorus Logo
  • Counter Logo
  • Cope Logo
  • STM Logo
Copyright © 2024 The American Society of Mechanical Engineers
Close Modal
This Feature Is Available To Subscribers Only

or Create an Account

Close Modal
Close Modal
This site uses cookies. By continuing to use our website, you are agreeing to our privacy policy.
Accept