Section
Resolution Product Category
Facilities Type
Related Technical Area
Image
NUREG 0933
Displaying 326 - 344 of 344
DESCRIPTION Historical Background The Office of Nuclear Reactor Regulation (NRR) identified this issue in April 1999, [1] when the concern was raised that licensees operating within the regulatory guidelines of Generic Letter (GL) 85-11, Completion of …
1
DESCRIPTION NRC regulatory requirements include the estimation of individual offsite dose from the design basis LOCA. The fission product source term in TID-14844 [1] which is referenced by the regulations, has historically been used for this application. …
1
DESCRIPTION Historical Background This issue was identified when it was believed [1] that the validity of steam generator (SG) tube leak and rupture analyses could be affected by resonance vibrations in steam generator tubes during steam line break …
1
DESCRIPTION Historical Background This generic issue was proposed [1] in response to SECY-00-198 [2] which explored means of risk informing 10 CFR 50.44. As a part of this effort, the paper recommended that safety enhancements that have the potential to …
1
DESCRIPTION The risk of failure from fatigue of various reactor coolant system components was studied under Issue 78 and later integrated into the NRR Fatigue Action Plan which was completed and documented in SECY-95-245. [1] The staff concluded that the …
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 Historical Background This issue was raised [1] by NRR and addresses the adequacy of the calculations, testing, and acceptance criteria related to the creation of a vacuum in the reactor building of a BWR, following an engineered safeguards …
1
DESCRIPTION Historical Background This issue was identified [1] , [2] by a Region III inspector and addressed the possible failure of low pressure emergency core cooling systems due to unanticipated, large quantities of entrained gas in the suction piping …
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 Historical Background The issue of potential hazards from combustible gases was raised [1] after two events involving hydrogen combustion occurred within 2 months in late-2001 at two foreign BWRs. Both these events involved sudden rupture of …
1
DESCRIPTION Historical Background This issue was raised [1] , [2] by an NMSS staff member whose concern arose from the observation that spent fuel pool racks using Boral for neutron absorption had experienced some problems with swelling and degradation of …
1
DESCRIPTION Historical Background This GI was proposed [1] in response to a concern raised by the ACRS in its May 21, 2004, report on the resolution of certain NUREG-1740 [2] items. The ACRS recommended that the staff develop a mechanistic understanding …
1
DESCRIPTION Historical Background This issue was initiated [1] in response to a recommendation in the screening analysis of Generic Issue (A) I-195, "Potential Hydrogen Combustion in BWR Piping." GI-195 investigated the potential safety …
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
DESCRIPTION Historical Background This issue was identified by RES after concern was raised for the number of component failures in the solid state protection systems of nuclear power plants that were caused by the growth of tin whiskers. [1] In 1987, …
1
DESCRIPTION Historical Background This issue was identified [1] by NRR following an allegation that was submitted to the NRC in March 2006 that described a scenario in which a SBLOCA event in a PWR has progressed to the sump recirculation mode of core …
1
DESCRIPTION Historical Background Spent fuel pools (SFPs) at PWRs are Seismic Category I structures that contain borated water, maintain spent fuel temperatures, and provide radiation shielding. The SFPs are typically lined with stainless steel plates, …
1
DESCRIPTION This issue was identified by an NMSS engineer in December 2006 and addressed concerns about potential safety issues with cranes that are used to lift spent fuel casks at nuclear power plants. The areas of concern involved questions about the …
1
Note: Due to the sensitive nature of some information in this analysis, redactions are necessary in this public version. The Nuclear Regulatory Commission (NRC) has coordinated with other Federal agencies (Department of Homeland Security, Federal Energy …
1
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.