Document: NRC Regulatory Guide
Document ID: 96ecfd93-e64a-4f35-93fe-d3b95daac61d
Document Type: regulatory_guide
Title: Monitoring the Effectiveness of Maintenance at Nuclear Power Plants + HISTORY –HISTORY 06/2018 – DG-1336 , Proposed Revision 4 09/2011 – DG-1278 , Proposed Revision 3 08/1996 – DG-1051 , Proposed Revision 2 06/1994 – DG-1031, Proposed Revision 1 11/1992 – DG-1020, Proposed Revision 0 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1812/ML18129A080.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.160
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Content:
rformance and condition monitoring activities and associated goals and preventive maintenance activities at least annually. In 1993, the NRC amended its regulations for monitoring the effectiveness of maintenance programs at commercial nuclear power plants (Final Rule, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, 58 FR 33,993 (June 23, 1993)). The 1993 amendment changed the time interval for conducting evaluations from a mandatory once-every-year to once-every-refueling-cycle (but not to exceed 24 months). Noting that the stresses on most SSCs in an operating plant are greater than those associated with a shutdown and defueled plant, the NRC later amended its rules to address decommission, and allowed the scope of items in the maintenance rule to be limited to those SSCs associated with the storage, control, and maintenance of spent fuel in a safe condition in a manner that provides reasonable assurance that the SSCs are capable of performing their intended function (Final Rule, Decommissioning DG-1336, Page 4 of Nuclear Power Reactors, 61 FR 39,278 (July 29, 1996). The NRC also amended 50.65 to reflect changes in 10 CFR 50.34(a)(1) and 10 CFR Part 100 concerning reactor site criteria (Final Rule, Reactor Site Criteria Including Seismic and Earthquake Engineering Criteria for Nuclear Power Plants, 61 FR 65,157 (Dec. 11, 1996)). The NRC also made several corrections to 50.65 (Final Rule, Definition of Safety-Related Structures, Systems, and Components; Technical Amendment, 62 FR 47,268 (Sept. 7, 1997); Final Rule, Minor Correcting Amendments, 62 FR 59,275 (Nov. 3, 1997)). In 1999, the NRC amended its power reactor safety regulations to require that licensees assess the effect of equipment maintenance on the plant's capability to perform safety functions before beginning maintenance activities on structures, systems, and components (SSCs) within the scope of the maintenance rule (Final Rule, Monitoring the Effectiveness of Maintenance at