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NUREG 0933
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Displaying 51 - 73 of 73
DESCRIPTION Historical Background This issue was raised [1] in March 1985 to address the staff's concern that there were no requirements for dynamic qualification testing or dynamic surveillance testing of large bore hydraulic snubbers (> 50 kips load …
1
DESCRIPTION Historical Background This issue was identified in a RRAB memorandum [1] in March 1985 and addressed the possibility of relay contact chatter during a seismic event and its resulting effect upon safety and safety-related electrical control …
1
DESCRIPTION Historical Background This issue was identified in a NRR/DST memorandum [1] and addressed the potential risk reduction that might result from training operators and having procedures developed to assist the operators in managing accidents …
1
On June 9, 1985, Davis-Besse had a partial loss of feedwater while operating at 90% power. Following a reactor trip, the loss of all feedwater occurred. The two OTSGs became dry and were ineffective as a heat sink. Consequently, the RCS pressure increased …
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 Since the TMI-2 accident in March 1979, to which human error was a major contributor, the issue of academic requirements for reactor operators has been a major concern of the NRC. In October 1985, the NRC issued a Policy Statement on …
1
DESCRIPTION Historical Background This issue was identified [1] by NRR when concerns were expressed that the seismic loading on equipment and pipe-mounted components may have been underestimated. These concerns could be divided into two sub- issues: …
1
DESCRIPTION Historical Background This issue arose as the result of an event at the Palo Verde Nuclear Generating Station (PVNGS) Unit 3 in which inadequate lighting conditions exacerbated an unrelated reactor trip. [1] During this event, half of the …
1
DESCRIPTION In 1977, the NRC initiated the Systematic Evaluation Program (SEP) to review the designs of 51 older, operating nuclear power plants. The SEP was divided into 2 phases. In Phase I, the staff defined 137 issues for which regulatory requirements …
1
In resolving GSIs over the years, the staff generally found it necessary to make assumptions and establish limitations on the scope of the issues. As a result of its review of the resolution of some GSIs, the ACRS expressed concerns that the assumptions …
1
DESCRIPTION Historical Background The NRC post-TMI-2 accident shift staffing policy was codified through the issuance of 10 CFR 50.54(m) which specified minimum requirements for licensed operators at nuclear power reactor sites but not for non-licensed …
1
DESCRIPTION Historical Background Beginning in the early-1980s, the NRC sponsored the development of a Probabilistic Seismic Hazard Analysis (PSHA) methodology by LLNL. For the purpose of conducting a systematic evaluation of the licensing criteria for …
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, …
1
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 …
1
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 …
1
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 …
1
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, …
1
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 …
1
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 …
1
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 …
1
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 …
1
This task, outlined in Chapter 1 of NUREG-1251, [1] called for the staff to review the administrative controls over plant operations in the U.S. to determine if adequate controls are in place to maintain plant conditions within the safe operating …
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, …
1
Page Last Reviewed/Updated 3/1/2026
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