findings and will not be the SDP. onditions performance are not may need to be addressed by other NRC processes (e.g., , Generic Safety Issue, rule-making). 03.0 Nothing in this guidance relieves any licensee from fully complying with Technical Specifications, licensing basis commitments, or other applicable regulatory requirements. Continued compliance with regulatory requirements maintains the requisite defense-in-depth and safety margins necessary to achieve adequate protection of public health and safety. 03.0 The significance of reactor events caused or complicated by equipment malfunction or operator error assessed by NRC in accordance with IMC 0309, Inspection Decision “Reactive Basis for Reactors” MD 8.3, Incident Investigation Program.” Although the product of this “NRC risk evaluation may provide useful risk insights to for event response or follow-up, it was not designed to determine the safety significance of . the SDP is used to estimate the significance of , including those that manifest themselves during events, associated with a reactor event should be 0609-04 DEFINITIONS 04.01 Applicable definitions are located in IMC 0612, Reactor Inspection Reports” “Power 04.02 Inspection findings are assigned a color representing the significance of the finding. The following definitions (04.02.a thru 04.02.d) include the quantitative and qualitative for each color and need to be applied appropriately to each SDP appendix listed at the end of this document. A graphical representation of the quantitative significance of findings is displayed in Exhibit 1.
findings and will not be the SDP. onditions performance are not may need to be addressed by other NRC processes (e.g., , Generic Safety Issue, rule-making). 03.0 Nothing in this guidance relieves any licensee from fully complying with Technical Specifications, licensing basis commitments, or other applicable regulatory requirements. Continued compliance with regulatory requirements maintains the requisite defense-in-depth and safety margins necessary to achieve adequate protection of public health and safety. 03.0 The significance of reactor events caused or complicated by equipment malfunction or operator error assessed by NRC in accordance with IMC 0309, “Reactive Inspection Decision Basis for Reactors” MD 8.3, “NRC Incident Investigation Program.” Although the product of this risk evaluation may provide useful risk insights to for event response or follow-up, it was not designed to determine the safety significance of . the SDP is used to estimate the significance of , including those that manifest themselves during events, associated with a reactor event should be 0609-04 DEFINITIONS 04.01 Applicable definitions are located in IMC 0612, “Power Reactor Inspection Reports” 04.02 Inspection findings are assigned a color representing the significance of the finding. The following definitions (04.02.a thru 04.02.d) include the quantitative and qualitative for each color and need to be applied appropriately to each SDP appendix listed at the end of this document. A graphical representation of the quantitative significance of findings is displayed in Exhibit 1.
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