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Appendix D Standards (Limits) Proposed by Other Organizations
Pages 199-211

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From page 199...
... total effective dose equivalent (TEDE) , above background, for clearance of materials from regulatory control.
From page 200...
... The magnitude of the potential collective doses to the critical group associated with the items in accordance with this standard is so low that additional ALARA evaluations or analyses, or further reductions in the primary dose standard, are not deemed necessary. INTERNATIONAL ATOMIC ENERGY AGENCY Safety Series No.
From page 201...
... Individuals do not usually consider variation in exposure to natural background radiation when considering moving 3The word trivial is used extensively by the IAEA in Vienna and the European commission in their safety guides when describing an individual effective dose equivalent in the range of lo to 100 mSv/yr (1 to 10 mrem/yr)
From page 202...
... in 1977 and is much lower than any upper bound set by competent authorities for practices subject to regulatory control. EUROPEAN COMMISSION Radiation Protection 89: Recommended Radiological Protection Criteria for the Recycling of Metals from the Dismantling of Nuclear Installations This document provides recommended radiological protection criteria for the recycling of metal arising from dismantling nuclear installations.
From page 203...
... AMERICAN NUCLEAR SOCIETY The American Nuclear Society (ANS) Special Committee on Site Cleanup and Restoration Standards is responsible for reviewing draft regulations from federal organizations related to the decommissioning of nuclear facilities and providing ANS input to the rulemaking process.
From page 204...
... European Union Directive 96/29/EURATOM allows clearance of "radioactive substances where the concentration of activity per unit mass do not exceed the exemption values set out in Column 3 of Table A to Annex I." Annex I is reproduced at the end of this appendix (see Table D-1) , as is a table of derived clearance levels based on a primary dose standard of 10 pSv/yr from NUREG1640 (Table D-2.
From page 205...
... MARSSIM's title includes the term "survey" because it provides information on planning and conducting surveys and the term "site investigation" because the process outlined in the manual allows one to begin by investigating any site that may involve radioactive contamination. The decommissioning that follows remediation requires a demonstration to the responsible federal or state agency that the cleanup effort was successful and that the release criterion (a specific regulatory limit)
From page 206...
... MARS SIM provides standardized and consistent approaches for planning, conducting, evaluating, and documenting environmental radiological surveys, with a specific focus on the final status surveys that are carried out to demonstrate compliance with cleanup regulations. TABLE D-1 Exempt Quantities Established by Council Directive 96/291EURATOM Quantity Concentration Quantity Concentration Nuclide (Bq)
From page 207...
... APPENDIX D TABLE D-1 continued 207 Quantity Concentration Quantity Concentration Nuclide (Bq)
From page 208...
... 208 TABLE D-1 continued APPENDIX D Quantity Concentration Quantity Concentration Nuclide (Bq)
From page 209...
... APPENDIX D TABLE D-1 continued 209 Quantity Concentration Quantity Concentration Nuclide (Bq)
From page 210...
... Radi on ucli de NRC (Bq/cm2)
From page 211...
... APPENDIX D 211 TABLE D-2 continued Mass Clearance Levels Radi on ucli de Ce-141 Ce- 144 Pm- 147 Eu-152 Eu-154 Eu-155 Re-186 Ir-192 Pb-210 Po-210 Bi-210 Rn-222 Ra-223 Ra-224 Ac-225 Ra-225 Ra-226 Ac-227 Th-227 Th-228 Ra-228 Th-229 Th-230 Surficial Clearance Levels NRC (Bq/g) 4.E+OO 3.E+OO 9.E+02 9.E-02 8.E-02 9.E+OO 4.E+01 8.E-02 7.E-02 2.E-O1 3.E+02 l.E-O1 6.E-O1 2.E-O1 7.E-O1 6.E+OO 6.E-02 3.E-02 2.E+OO 8.E-02 l.E-O1 2.E-02 2.E-O1 Radi on ucli de NRC (Bq/cm2)


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