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NUREG 0933
Displaying 201 - 210 of 210
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 …
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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, …
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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 …
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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 …
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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 …
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The Chernobyl Unit 4 accident was a prompt critical reactivity excursion that occurred when the operators reduced power to well below the permissible safe operating level and, at the same time, neglected to follow low power operating procedures. Unit 4 …
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The Chernobyl accident, with its absence of effective containment, has focused attention on the strengths and performance limits of the substantial containments for U.S. LWRs. It has led to added recognition of the significance of ongoing work on the …
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A number of facts about the Chernobyl accident have some bearing on emergency planning and preparedness around U.S. commercial nuclear power plants. This task, outlined in Chapter 4 of NUREG-1251, [1] called for the staff to examine the implications of …
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The highly energetic reactivity excursion accident at Chernobyl mechanically disrupted the core, rapidly vaporized the water coolant with which the fragmented fuel came into contact, and generated combustible hydrogen by chemical reaction of core …
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The Fort St. Vrain HTGR and DOE's N-reactor at the Hanford Reservation in Washington State are the only graphite-moderated power reactors operating in the U.S. This task, outlined in Chapter 6 of NUREG-1251, [1] called for the staff to assess the HTGR …
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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.