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'''XI.M23 INSPECTION OF OVERHEAD HEAVY LOAD AND LIGHT LOAD (RELATED TO REFUELING) HANDLING SYSTEMS''' | '''XI.M23 INSPECTION OF OVERHEAD HEAVY LOAD AND LIGHT LOAD (RELATED TO REFUELING) HANDLING SYSTEMS''' | ||
'''Program Description''' | '''Program Description''' | ||
Latest revision as of 20:59, 4 October 2024
XI.M23 INSPECTION OF OVERHEAD HEAVY LOAD AND LIGHT LOAD (RELATED TO REFUELING) HANDLING SYSTEMS
Program Description
The Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems program evaluates the effectiveness of maintenance monitoring activities for cranes and hoists that are within the scope of license renewal. This program addresses the inspection and monitoring of crane-related structures and components to provide reasonable assurance that the handling system does not affect the intended function of nearby safety-related equipment. Many crane systems and components are not within the scope of this program because they perform an intended function with moving parts or with a change in configuration, or they are subject to replacement based on qualified life.
The program includes periodic visual inspections to detect loss of material due to general corrosion and wear, deformed or cracked bridges, structural members, and structural components; and loss of material due to general corrosion, cracking and loss of preload on bolted connections. NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants," provides specific guidance on the control of overhead heavy load cranes. The activities to manage aging effects specified in this program utilize the guidance provided in American Society of Mechanical Engineers (ASME) Safety Standard B30.2, “Overhead and Gantry Cranes (Top Running Bridge, Single or Multiple Girder, Top Running Trolley Hoist),” which is referenced by NUREG–0612, or other appropriate standards in the ASME B30 series. In addition, monitoring and maintenance of structural components of crane handling systems follow the maintenance rule requirements provided in Title 10 of the Code of Federal Regulations (10 CFR) 50.65 for other crane types.
Evaluation and Technical Basis
- 1. Scope of Program: The program manages the aging effects associated with handling systems that are within the scope of 10 CFR 54.4. Portions of the handling system that are within the scope of this program include the bridges, structural members, and structural components.
- 2. Preventive Actions: This program is a condition monitoring program. No preventive actions are identified.
- 3. Parameters Monitored or Inspected: Surface condition is monitored by visual inspection to provide reasonable assurance that loss of material is not occurring due to general corrosion or wear and the bridges, structural members, and structural components do not exhibit deformation or cracking. In addition, bolted connections are monitored for loss of material, cracking, and loose bolts, missing or loose nuts, and other conditions indicative of loss of preload.
- 4. Detection of Aging Effects: Load handling systems are visually inspected at a frequency in accordance ASME B30.2, “Overhead and Gantry Cranes (Top Running Bridge, Single or Multiple Girder, Top Running Trolley Hoist),” or other appropriate standard in the ASME B30 series. ASME B30.2 establishes inspection frequencies based on the severity of service, as defined by the number and magnitude of lifts. For systems that are infrequently in service, such as containment polar cranes, periodic inspections are performed once every refueling cycle just prior to use. Visual inspections consist of the following:
- Bridges, structural members, and structural components are visually inspected for loss of material due to general corrosion; deformation; cracking, and wear.
- Bolted connections are visually inspected for loss of material due to general corrosion; cracking; and loose or missing bolts or nuts, and other conditions indicative of loss of preload.
- Visual inspection activities are performed by personnel qualified in accordance with plant-specific procedures and processes.
- 5. Monitoring and Trending: Deficiencies are documented using plant-specific processes and procedures, such that results can be trended; however, the program does not include formal trending.
- 6. Acceptance Criteria: Any visual indication of loss of material, deformation, or cracking, and any visual sign of loss of bolting preload is evaluated according to ASME B30.2 or other applicable industry standard in the ASME B30 series.
- 7. Corrective Actions: Results that do not meet the acceptance criteria are addressed in the applicant’s corrective action program under those specific portions of the quality assurance (QA) program that are used to meet Criterion XVI, “Corrective Action,” of 10 CFR Part 50, Appendix B. Appendix A of the Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the corrective actions element of this aging management program (AMP) for both safety-related and nonsafety-related structures and components (SCs) within the scope of this program.
- Repairs are performed as specified in ASME B30.2 or other appropriate standard in the ASME B30 series.
- 8. Confirmation Process: The confirmation process is addressed through those specific portions of the QA program that are used to meet Criterion XVI, “Corrective Action,” of 10 CFR Part 50, Appendix B. Appendix A of the GALL-SLR Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the confirmation process element of this AMP for both safety-related and nonsafety-related SCs within the scope of this program.
- 9. Administrative Controls: Administrative controls are addressed through the QA program that is used to meet the requirements of 10 CFR Part 50, Appendix B, associated with managing the effects of aging. Appendix A of the Appendix A of the GALL-SLR Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the administrative controls element of this AMP for both safety-related and nonsafety-related SCs within the scope of this program.
- 10. Operating Experience: There has been no history of corrosion-related degradation that threatened the ability of a crane to perform its intended function. Likewise, because cranes have not been operated beyond their design lifetime, there have been no significant fatigue-related structural failures. Operating experience indicates that loss of bolt preload has occurred, but not to the extent that it has threatened the ability of a crane structure to perform its intended function.
- The program is informed and enhanced when necessary through the systematic and ongoing review of both plant-specific and industry operating experience including research and development such that the effectiveness of the AMP is evaluated consistent with the discussion in Appendix B of the GALL-SLR Report.
References
10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” Washington, DC: U.S. Nuclear Regulatory Commission. 2016.
10 CFR 54.4, “Scope.” Washington, DC: U.S. Nuclear Regulatory Commission. 2015.
ASME. Safety Standard B30.2, “Overhead and Gantry Cranes (Top Running Bridge, Single or Multiple Girder, Top Running Trolley Hoist).” New York, New York: American Society of Mechanical Engineers. 2005.
US NRC. Generic Letter 80-113, “Control of Heavy Loads.” Agencywide Documents Access and Management System (ADAMS) Accession No. ML071080219. Washington, DC: U.S. Nuclear Regulatory Commission. December 22, 1980.
_____. Generic Letter 81-07, “Control of Heavy Loads.” ADAMS Accession No. ML031080524. Washington, DC: U.S. Nuclear Regulatory Commission. February 3, 1981.
_____. NUREG–0612, “Control of Heavy Loads at Nuclear Power Plants.” ADAMS Accession No. ML070250180. Washington, DC: U.S. Nuclear Regulatory Commission. July 31, 1980.
_____. Regulatory Guide 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” Revision 2. ADAMS Accession No. ML003761662. U.S. Nuclear Regulatory Commission, March 31, 1997.