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NUREG 0933
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This task was developed to assure that the number and capabilities of the staff at nuclear power plants are adequate to provide safe operation. To meet this goal, consideration will be given to: (1) the numbers and functions of the staff needed to safely …
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In response to Section 306 of the Nuclear Waste Policy Act of 1982, the Commission published a "Policy Statement [1] on Training and Qualification of Nuclear Power Plant Personnel, March 1985. This Policy Statement endorsed the INPO Accreditation Program …
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One purpose of this task is to ensure that the licensing examination for reactor operators and senior operators is a valid measure of the operator's knowledge and ability to perform the necessary tasks and functions required to safely operate and control …
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This task was developed to provide assurance that plant procedures were adequate and could be used effectively. The objective was to provide procedures that would guide operators in maintaining plants in a safe state under all operating conditions, …
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The objective of this task was to ensure that the man-machine interface (MMI) is adequate for the safe operation and maintenance of nuclear power plants. This objective was to be attained by developing: (1) human factors engineering guidelines for …
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The objective of this effort is to develop tested technology to assess the capability and adequacy of utility management and organization to provide for safe operation of their nuclear power plants. This objective will be accomplished by: (1) developing …
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The primary purposes of this task are to develop a technical support system for NRC reliability evaluations, especially the PRA programs, and to provide feedback links from operating experience to other elements of the human factors program. A secondary …
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Historical Background The purpose of the Maintenance and Surveillance Program (MSP) effort is to provide direction for the NRC's efforts to assure effective nuclear power plant maintenance. The program will be based on the current NRC regulatory approach …
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The following is an excerpt from Appendix VI, Section 2 of WASH-1400 (NUREG-75/104), "Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," dated October 1975. On this page: Section 2 Releases from …
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The table below identifies those generic issues (GIs) that have resulted in a regulatory product: hence, they may be applicable to operating and future nuclear power plants. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) …
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TABLE 1 RISK THRESHOLDS (a) The priority rank is always HIGH when any of the following risk (or risk related) thresholds are estimated to be exceeded (or when extraordinary uncertainty suggests that they may well be exceeded): (1) 11000 person-rem …
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This appendix documents those activities related to generic issues, i.e., related generic activities (RGA) that did not meet the criteria for designation as generic issues (GI) but were important enough to require the development of Action Plans by NRR to …
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This appendix documents those generic communication and compliance activities (GCCA) completed by NRR that did not meet the criteria for designation as generic issues (GI), but were important enough to require the issuance of Information Notices (IN) …
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This appendix documents those non-reactor GSIs identified, prioritized, and resolved by NMSS. As stated in SECY-98-001, [1] the prioritization procedure for these issues is contained in NMSS Policy and Procedures Letter 1-57, [2] "NMSS Generic Issues …
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BACKGROUND I. History On October 8, 1976, the Commission directed the staff to develop "a program plan for resolution of generic issues (GIs) and completion of technical projects." The Commission further requested that "this plan should include: task …
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Page Last Reviewed/Updated 3/1/2026
Disclaimer: Some of the formatting in NUREG-0933 may not be correct. We are currently working on fixing the formatting.