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NUREG 0933
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DESCRIPTION Historical Background Experiments conducted at several test facilities prior to 1984 showed that irradiated fuel can fragment (crumble) into small pieces during a LOCA. Some evaluation of this effect was made for NRC by EG&G. [1] Although it …
1
DESCRIPTION Historical Background This concern was raised by an NRC resident inspector who questioned the practice of leaving the refueling canal drain valve in the closed position during operations at H. B. Robinson Unit 2. [1] A subsequent investigation …
1
DESCRIPTION Historical Background Issue B-63, which was resolved and implemented as MPA B-45, required leak-testing of the check valves that isolate those low pressure systems that are connected to the RCS outside the containment. However, except for …
1
DESCRIPTION Historical Background Combustible gases such as H 2 , propane, and acetylene are used during normal operations of nuclear power plants in limited quantities and for relatively short periods of time. H 2 , the most prevalent of these gases in …
1
DESCRIPTION Historical Background This issue was identified in a DST/NRR memorandum [1] which addressed a condition in which some protective devices intended to trip active engineered safety features (ESF) components, under indication of equipment …
1
DESCRIPTION The loss of all feedwater event at Davis-Besse on June 9, 1985, resulted in the formation of an NRC project team to investigate the event. The team's findings were published in NUREG-1154 [1] and were subsequently reviewed by DL/NRR. As a …
1
DESCRIPTION Historical Background This issue was identified [1] by NRR as a result of concern for the potential loss of the RHR system under a harsh containment environment. The RHR system is normally located outside the containment and is not required to …
1
DESCRIPTION Historical Background Large-break loss-of-coolant accidents (LBLOCA) with consequential steam generator tube ruptures (SGTR) was identified as a GSI in a DRPS/RES memorandum [1] on April 28, 1987. The issue surfaced as a result of the proposed …
1
DESCRIPTION Historical Background This issue was identified as an alternative approach to the Finding 15 recommendation [1] discussed in Issue 125.I.5, "Safety Systems Tested in All Conditions Required by DBA," which states that "[t]horough integrated …
1
DESCRIPTION Historical Background This issue was identified [1] by NRR following the issuance of NRC Information Notice (IN) 93-17 [2] which was based in part on a deficiency in the Surry Power Station emergency diesel generator (DG) loading. This …
1
DESCRIPTION Historical Background This issue was identified [1] following an NRR request for reconsideration of the safety priority ranking (DROP) of GSI-22, "Inadvertent Boron Dilution Events," based on new information on high burn-up fuel and new …
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
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 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 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
Page Last Reviewed/Updated 3/1/2026
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