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NUREG 0933
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Displaying 26 - 35 of 35
DESCRIPTION Following the NRR reorganization in November 1985, EIB/DSRO was responsible for resolving three issues that were directly related to onsite electrical systems: Issue 48, "LCO for Class 1E Vital Instrument Buses in Operating Reactors"; Issue …
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DESCRIPTION Historical Background This issue was identified [1] when the staff found the Byron Unit 1 vulnerable to core-melt sequences in the absence of the availability of Byron Unit 2 which was not yet operational. Because of the licensing status of …
1
DESCRIPTION Historical Background In IE Circular No. 80-02, [1] the concern of overtime work for licensee staff who perform safety-related functions was discussed and limits on maximum working hours were recommended. In July 1980, a letter [2] was issued …
1
DESCRIPTION Historical Background This issue was identified in a DSIR/RES memorandum [1] which addressed the concern for the reliability of breakers used to trip the recirculation pumps at high pressure or low water level signals during ATWS mitigation in …
1
The results of ongoing staff-sponsored research which culminated in the assessment of risk at five U.S. nuclear reactors (NUREG-1150 [1] ) indicated that, for the Peach Bottom MARK I containment, the core-melt probability was relatively low. However, it …
1
Issue Identification The NRC identified [1] this issue in June 1992 to address an NRC staff members concern, given in a DPO dated December 3, 1991, [2] and modified March 27, 1992, [3] about the potential for a main steamline break (MSLB) accident to …
1
DESCRIPTION The NRC requires that a licensee operate its facility in compliance with the NRC's regulations and the specific facility's license. When a licensee fails to comply with the conditions of its license or the NRC's regulations, the staff will …
1
EXECUTIVE SUMMARY The issue of potential blockage in the containment sumps was first identified in Unresolved Safety Issue (USI) A-43, "Containment Emergency Sump Performance." It identified a concern for the availability of adequate recirculation cooling …
1
DESCRIPTION On May 26, 2005, the Office of Nuclear Reactor Regulation (NRR), Division of Engineering, recommended that issues related to closed Generic Issue (GI)-194, "Implications of Updated Probabilistic Seismic Hazard Estimates," dated September 23, …
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DESCRIPTION On May 26, 2005, the Office of Nuclear Reactor Regulation (NRR), Division of Engineering, recommended that issues related to closed Generic Issue (GI)-194, "Implications of Updated Probabilistic Seismic Hazard Estimates," dated September 23, …
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Page Last Reviewed/Updated 3/1/2026
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