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NUREG 0933
Displaying 126 - 150 of 162
DESCRIPTION Historical Background As identified in NUREG-0471, [1] this issue involved staff evaluations of vendors' data and approaches for determining LOCA heat sources and developing staff positions as needed. The contributors to LOCA heat sources, …
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DESCRIPTION Combinations of fabrication, stress, and environmental conditions have resulted in isolated instances of stress corrosion cracking of low pressure Schedule 10 Type 304 stainless steel piping systems. Although these systems are not part of a …
1
DESCRIPTION Historical Background Dose calculations by AAB/NRR in 1975 indicated that operation of the main steam isolation valve leakage control system (MSIVLCS) required for some BWRs could result in higher offsite accident doses than if the system were …
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DESCRIPTION Historical Background A BWR RHR system is designed for: (1) containment spray/suppression pool cooling, (2) fuel pool cooling augmentation, (3) low pressure coolant injection, and (4) bringing the reactor down to a cold shutdown condition. …
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DESCRIPTION This NUREG-0471 [1] task will respond to a concern of the ACRS about the effectiveness of various containment sprays to remove airborne radioactive materials which could be present within the containment following a LOCA. This concern has been …
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DESCRIPTION Historical Background The operating experience of nuclear power plants indicates that a number of valves, valve operators, and pumps fail to operate as specified in the technical specifications either under testing conditions or when they are …
1
DESCRIPTION Historical Background Structural damage to the primary system, including the reactor pressure vessel and internals, associated piping and steam generator tubing in PWRs, can be caused by vibrations of sufficient magnitude. These vibrations can …
1
DESCRIPTION This NUREG-0471 [1] item was an ACRS generic concern that initially addressed the common mode failure of identical components exposed to identical or nearly-identical conditions or environments. This concern was later expanded to include other …
1
DESCRIPTION Licensees are required to estimate the design-basis flood levels for each nuclear power plant site consistent with the requirements in General Design Criterion 2, "Design Bases for Protection against Natural Phenomena," of Appendix A, "General …
1
DESCRIPTION SRP [1] Section 15.7.3 requires an analysis of the consequences of failure of tanks containing radioactive liquids outside containment. This NUREG-0471 [2] task involves the development of a NUREG report that will describe a consistent and …
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DESCRIPTION Interpretations of NEPA require the environmental impact assessment include land use impacts and alternatives in nuclear power plant licensing cases. The staff has performed both economic and non-economic land resource assessments in …
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DESCRIPTION There are no current criteria for acceptability of solidification agents. This NUREG-0471 [1] task involves the development of criteria for acceptability of radwaste solidification agents to properly implement a process control program for the …
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DESCRIPTION Historical Background This issue is described in NUREG-0471 [1] and was raised by the ACRS who recommended that studies be made of the technique for seismic scram and the potential safety advantages and disadvantages of prompt reactor scram, …
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DESCRIPTION This issue was documented in NUREG-0471 [1] and stemmed from an ACRS recommendation that the staff explore diverse means of obtaining ECCS capability for future plants. The ACRS also recommended the staff explore the issue in the context of …
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DESCRIPTION This NUREG-0471 [1] item is an ACRS generic concern which involves assessing the uncertainties in calculations of the control rod drop accident, including the choice of negative reactivity insertion rate due to a scram and the potential …
1
DESCRIPTION During the administration of the third of a three-fraction vaginal treatment of a patient on January 9, 1996, the treatment console of a Nucletron high-dose-rate (HDR) remote afterloader unit locked up, and the console alarm sounded when the …
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DESCRIPTION This issue was identified [1] by NMSS after several cases were reported where licensees found residual contamination remaining in some components of Krypton-85 handling systems after the standard decommissioning process. The staff's concern …
1
DESCRIPTION This issue was identified [1] by NMSS with the discovery of intergranular corrosion in one manufacturer's 316L stainless steel source used in Category IV irradiator pools. Analysis of data and reports provided by the manufacturer revealed that …
1
DESCRIPTION This issue was identified [1] by NMSS after Cobalt-60 radiography sources were stolen from a bankrupt licensee (Larpen of Texas) and sold to a scrap yard where one source fell out of its housing and exposed several individuals. The Bureau of …
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DESCRIPTION This issue was identified [1] by NMSS when Victoreen, Inc., notified the NRC that some of its Model 530 and 530SI Electrometer/Dosimeter instruments were susceptible to developing cracks in their internal resistor networks. These cracked …
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DESCRIPTION This issue was identified [1] by NMSS and addresses the potential for special nuclear material containing unusual moderators to re-concentrate and form a critical mass in low-level waste disposal systems. The results of studies of two …
1
DESCRIPTION The importance of computer software (methods and data) in establishing the criticality safety of systems with fissile material is increasing as licensees work to optimize facilities and storage/transport packages at the same time that access …
1
DESCRIPTION The Year 2000 computer problem had the potential to pose a threat to public health, site safety and safeguards, and worker safety. Many computer systems could have potentially failed to recognize the change to a new century. The staff believed …
1
DESCRIPTION This issue was identified [1] by NMSS after three reports of radiography source disconnects involving drive cable breaks in Amersham equipment were reported. IN 97-91 [2] was issued to alert all industrial radiography licensees to potential …
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DESCRIPTION This issue was identified [1] by NMSS after it was reported in June 1997 that the source from a Troxler moisture density gauge broke off the source rod and was left at a temporary job site. Prior to this event, there had been 6 known …
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Page Last Reviewed/Updated 3/1/2026
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