Document: NRC Regulatory Guide
Document ID: 626cd346-6298-4966-a92d-c5d4b24bbc2b
Document Type: regulatory_guide
Title: Overhead Crane Handling Systems for Nuclear Power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1303/ML13038A096.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.104
CFR Part: 
CFR Title: 

Content:
est, the dummy load should be increased beyond the design rated load 1.5 percent per degree F temperature difference. ,Test frequency should be approximately 40 months or less; however, crane handling systems that are used less frequently than once every 40 months may be given a cold proof test prior to each use. The cold proof test should be followed by a nondestructive examination of critical areas for cracks. 5. Quality Assurance a. To the extent necessary, applicable pro- curement documents should require the crane manufac- turer to provide a quality assurance program consistent with the pertinent provisions of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50. b. The program should also address each of the recommendations in regulatory positions C.1, C.2, C.3, and C.4. D. IMPLEMENTATION The purpose of this section is to provide informa- tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. I. Except in those cases in which the applicant proposes an alternative method for complying with spec- ified portions of the Commission's regulations, this guide will be used in the evaluation of design, fabrication, as- :•ulirig, and use of crane systems for critical load handling ordered after September 1, 1976. 2. For crane handling systems ordered prior to September 1, 1976: a. Regulatory positions C.1, C.2. C.3, and C4 will be used in evaluating crane handling systems that have been ordered but are not yet assembled. b. All regulatory positions except C.I.f: C.3.c, f, and q will be used in evaluating crane handling systems that have been assembled or may have been used for handling heavy loads during plant construction. Regula- tory positions C.l.f; C.3.c, f, and q will be used by the NRC staff to determine the extent of changes or modifi- cations necessary. c. All regulatory positions except C. I.f; C.2.a, b, c, and d; C.3.a, b, c, e, f, g. j. n, o, p, q, r.