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NUREG 0933
Displaying 1 - 25 of 27
The objective of this task was to enhance public safety and reduce individual and societal risk by developing and implementing a phased program to include, in safety reviews, consideration of core degradation and melting beyond the design basis. ITEM …
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TASK III.D.1: RADIATION SOURCE CONTROL The objective of this task is to perform evaluations to establish additional design features that should be included in the rulemaking proceeding of Item II.B.8. The purpose of these evaluations is to identify design …
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The objective of this task was to improve public radiation protection in the event of a nuclear power plant accident by improving (1) radioactive effluent monitoring, (2) the dose analysis for accidental releases of radioiodine, tritium, and carbon-14, …
1
The objective of this task is to improve nuclear power plant worker radiation protection to allow workers to take effective action to control the course and consequences of an accident, as well as to keep exposures as low as reasonably achievable (ALARA) …
1
The objective of this task is to respond to the President's request for NRC participation in the Radiation Policy Council. ITEM IV.H.1: NRC PARTICIPATION IN THE RADIATION POLICY COUNCIL DESCRIPTION The Radiation Policy Council, a policy coordinating body …
1
DESCRIPTION Historical Background Operation of a LWR results in slow corrosion of the interior metal surfaces of the primary coolant system. The resulting corrosion products circulate through the reactor core and are activated by neutron flux from the …
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DESCRIPTION At the time this issue was identified in NUREG-0371, [1] compliance with NEPA required that alternatives to a proposed Federal action be considered, and that required alternatives be balanced against the base case in terms of their associated …
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DESCRIPTION Historical Background This NUREG-0371 [1] item involves the development of consistent and formalized acceptance criteria regarding the conversion to higher density storage racks (increased storage capacity) in existing spent fuel storage …
1
DESCRIPTION At all nuclear plants, overhead cranes are used to lift heavy objects in the vicinity of spent fuel. If a heavy object such as a spent fuel shipping cask or shielding block were to fall onto spent fuel in the storage pool or reactor core …
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DESCRIPTION This NUREG-0471 [1] task will develop more reliable models and associated computer capability than currently available to the staff for assessing the radiological consequences of accidents that could result in the releases of radioactivity …
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DESCRIPTION This NUREG-0471 [1] task involved the preparation of a paper detailing the bases for design basis flood events utilized by the staff in case reviews, including probable maximum floods, hurricanes, tsunamis, seiches, seismically-induced dam …
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DESCRIPTION Historical Background This issue, as originally stated in 1978, [1] addressed the unavailability (at that time) of a suitable model to predict the erosion rates and, therefore, the flood hydrographs at nuclear power plant sites resulting from …
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DESCRIPTION This NUREG-0471 [1] task involves the maintenance and improvement of calculational capabilities for assessing doses to individuals from radiation and radioactive effluents from normal operation and from radioactive releases from postulated …
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DESCRIPTION Practice in health impact assessments at the time of identification of this issue was to convert radiation exposure estimates into estimates of health effects, such as cancer deaths, illness, and life shortening. However, the models that were …
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DESCRIPTION Historical Background The containment flooding issue stems from a flooding event that occurred at the Indian Point 2 reactor in October 1980. [1] A large quantity of water leaked from fan coolers onto the containment building floor and …
1
DESCRIPTION Historical Background On November 11, 1981, the DAILY REPORT-REGION I carried a "prompt report" from Calvert Cliffs Units 1 and 2 indicating the licensee had been notified that the water tight integrity of the service water pump rooms in both …
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DESCRIPTION Historical Background The risks of beyond design basis accidents in the spent fuel storage pool were examined in WASH-1400 [1] (App. I, pp. I-96ff). It was concluded that these risks were orders of magnitude below those involving the reactor …
1
DESCRIPTION Historical Background Over the past several years, the NRC staff has noted an unacceptably large number of overexposures and uncontrolled exposures associated with pressurized water reactor cavity entries while incore detectors were withdrawn. …
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DESCRIPTION Historical Background The issue of using the most recent NOAA procedures for determining probable maximum precipitation (PMP) was raised [1] after an OL applicant disputed the NRC use of NOAA Hydrometeorological Report (HMR) Nos. 51 [2] and …
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DESCRIPTION The TMI-2 Safety Advisory Board was established to provide the licensee, General Public Utilities Nuclear Corporation, with a qualified, independent appraisal of the cleanup of TMI-2, with particular emphasis on the assurance of public and …
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In November 1992, two engineers who had previously worked under contract for the Pennsylvania Power and Light Company (PP&L) filed a report contending that the design of the Susquehanna station failed to meet regulatory requirements with respect to …
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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 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 …
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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 …
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Page Last Reviewed/Updated 3/1/2026
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