#REACTOR OVERSIGHT PROCESS LICENSE#
Management Meeting Routine Resident Inspector Interaction SRI/BC Meet with Licensee DD/RA Meet with Licensee Management EDO (or Commission) Meet with Senior License Management Commission Meeting with Senior Licensee Management Licensee Action Licensee Corrective Action with NRC Oversight Licensee Self Assessment with NRC Oversight Licensee Performance Improvement Plan with NRC Oversight NRC Inspection Risk-Informed Baseline Inspection Program Inspection Followup Baseline and Inspection Focused on Cause of Degradation Baseline and Team Insp. These data would provide a more comprehensive picture of plant performance and provide insights into aspects of the plants' safety culture that otherwise are not readily available on the Web site.ACTION MATRIX INCREASING SAFETY SIGNIFICANCE One or Two inputs White (in different cornerstones) in a Strategic Performance Area Cornerstone objectives fully met One Degraded Cornerstone (2 W or 1 Y input) or any 3 W inputs in strategic performance area Cornerstones met-minimal reduction in safety margin Repetitive/multiple degraded cornerstones, Multiple Y or 1 R input Cornerstone metlongstanding issues or signif safety margin reduction Overall Unacceptable Performance Operation not permitted. In the absence of performance indicators or other performance metrics for plants' safety culture, the NRC commissioners should make publicly available, through the ROP Web site, consolidated and comprehensive data on the plants that have substantive cross-cutting issues open. After completion of the initial 18-month implementation period, NRC plans to add additional performance metrics to IMC 0307 in an effort to effectively monitor and trend licensee performance. NRC also added specific questions to its internal and external ROP self-assessment surveys to solicit feedback on the safety culture effort.
#REACTOR OVERSIGHT PROCESS MANUAL#
In March 2009, NRC issued revised Inspection Manual Chapter 0307 entitled "Reactor Oversight Process (ROP) Self-Assessment Program" to add a specific measure to determine the effectiveness of the safety culture initiative. The indicators could also provide useful information to the public and other NRC stakeholders on the safety culture at plants. Trends in these performance indicators could be useful feedback to NRC on its safety culture activities. Given its importance to improving NRC's ability to identify declining safety performance at nuclear power plants before significant safety problems develop, the NRC commissioners should, in addition to periodically evaluating the effectiveness of its safety culture efforts, through its performance indicator program, develop specific indicators to measure important aspects of plants' safety culture.
Finally, also in January 2009, NRC issued revised IP 95003 to provide guidance on how NRC will provide a graded safety culture assessment.
Fourth, in January 2009, NRC issued revised IMC 0305 that included several safety culture related changes, including guidance for NRC regional offices regarding the inspections that can be performed to gather insights on how a licensee is addressing its repetitive substantive cross-cutting issue. Third, in December 2008, NRC issued revised Inspection Manual Chapter (IMC) 0612, "Power Reactor Inspection Reports to address the audit group's insights. Second, NRC extensively modified its inspection procedure (IP) 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input" by adding guidance to describe how NRC will (1) evaluate a licensee's safety culture assessment and (2) perform its own assessment of the licensee's safety culture. First, NRC completed an 18-month initial implementation period for monitoring and evaluating the effectiveness of its actions to incorporate safety culture into the Reactor Oversight Process.
NRC has taken several actions to implement this recommendation.
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