skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1

Abstract

Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology.

Authors:
;
Publication Date:
Research Org.:
Envirosphere Co., New York (USA); Nuclear Regulatory Commission, Washington, DC (USA)
OSTI Identifier:
6213595
Report Number(s):
NUREG/CR-4370-Vol.1
ON: TI86005817
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; LOW-LEVEL RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; RADIOACTIVE WASTE DISPOSAL; COMPUTERIZED SIMULATION; COST; ENVIRONMENTAL IMPACTS; REGULATIONS; SOURCE TERMS; MANAGEMENT; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SIMULATION; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; 052002* - Nuclear Fuels- Waste Disposal & Storage; 053000 - Nuclear Fuels- Environmental Aspects

Citation Formats

Oztunali, O.I., and Roles, G.W. Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1. United States: N. p., 1986. Web. doi:10.2172/6213595.
Copy to clipboard
Oztunali, O.I., & Roles, G.W. Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1. United States. doi:10.2172/6213595.
Copy to clipboard
Oztunali, O.I., and Roles, G.W. Wed . "Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1". United States. doi:10.2172/6213595. https://www.osti.gov/servlets/purl/6213595.
Copy to clipboard
@article{osti_6213595,
title = {Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1},
author = {Oztunali, O.I. and Roles, G.W.},
abstractNote = {Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology.},
doi = {10.2172/6213595},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}
Copy to clipboard
Technical Report:
View Technical Report (37.69 MB)
DOI:  10.2172/6213595
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • ; ; ; ...
    Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct humanmore » contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 2 describes the computer codes written to implement the updated analysis methodology plus provides some example problems. The computer codes are written for operation on an IBM personal computer, and are available from the Radiation Shielding Information Center at Oak Ridge National Laboratory.« less

  • ; ;
    Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on Probabilistic Accident Consequence Uncertainty Analysis by the United States Nuclear Regulatory Commission and the Commission of European Communities.

  • ;
    This report describes the methodology and computer program used by NRC to evaluate radiological impacts associated with petitions to have specific slightly contaminated radioactive waste streams designated as ''below regulatory concern.'' These wastes could be treated and disposed of at facilities which are not licensed for low-level radioactive waste management. The IMPACTS-BRC computer program is implemented on IBM-PC microcomputers using the FORTRAN programming language. Radiological impacts (doses) are estimated for several pathways including direct gamma radiation exposure, worker inhalation and exposure, offsite atmospheric and water releases, and intruder exposures. Annual impacts are calculated for the maximum individual, critical groups, andmore » general population. The treatment and disposal options include onsite incineration, incineration at municipal and hazardous waste facilities, and disposal at sanitary landfills and hazardous waste landfills. Modifications to the program (from Volume 1) are primarily for microcomputer compatibility and to provide information needed to evaluate the petitions. Default environmental and facility parameters are developed representing conservative assumptions about site selection and operational procedures. In particular, the parameters of the groundwater pathway model are modified to represent more conservative assumptions than the original model (Volume 1).« less

  • ;
    The methodological framework and program plan for systematic quantification and propagation of uncertainties in radiological source terms for light water reactors are presented. The QUASAR methodology is based on detailed sensitivity analysis of the Source Term Code Package (STCP), followed by a systematic uncertainty analysis on the most sensitive parameters/variables, and phenomenological issues related to prediction of radiological releases to the environment.

  • ; ; ; ...
    The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 1 comprises three parts. Part I reviews the methods currently utilized for seismic qualification of nuclear plant equipment with emphasis on qualification by testing. In this review various anomalies that are associated with qualification are identified. Part II provides an in-depth evaluation of the technical issues/anomalies previously identified. Part III providesmore » an evaluation of the method applicable to line mounted items; e.g., valves.« less