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assurance program was developed. If any portion of the written procedures or instructions is superseded, the licensee, certificate holder, and applicant for a CoC shall retain the superseded material for three years after it is superseded.

I.Audits. The licensee, certificate holder, and applicant for a CoC shall carry out a comprehensive system of planned and periodic audits to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program. The audits must be performed in accordance with written procedures or checklists by appropriately trained personnel not having direct responsibilities in the areas being audited. Audited results must be documented and reviewed by management having responsibility in the area audited. Follow-up action, including re-audit of deficient areas, must be taken where indicated.

AUTHORITY NOTE:Promulgated in accordance with R.S. 30:2104.B and 2113.

HISTORICAL NOTE:Promulgated by the Department of Environmental Quality, Office of the Secretary, Legal Affairs Division, LR 34:2112 (October 2008).

§1599.Appendix—Incorporation by Reference of 10 CFR Part 71, Appendix A, Tables A-1, A-2, A-3, and A-4; Procedures for Determining A1 and A2 [Formerly §1517]

A.Tables A-1, A-2, A-3, and A-4 in 10 CFR Part 71, Appendix A, January 1, 2007, are hereby incorporated by reference. These tables are used to determine the values of A1 and A2, as described in Subsections B-F of this Section.

B.Values of A1 and A2 for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in Table A-1. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) value. The Terabecquerel values are the regulatory standard. The curie values are for information only and are not intended to be the regulatory standard. Where values of A1 and A2 are unlimited, the values are for radiation control purposes only. For nuclear criticality safety, some materials are subject to controls placed on fissile material.

C.For individual radionuclides whose identities are known, but which are not listed in Table A-1, the A1 and A2 values contained in Table A-3 may be used. Otherwise, the licensee shall obtain prior U.S. NRC approval of the A1 and A2 values for radionuclides not listed in Table A-1, before shipping the material. For individual radionuclides whose identities are known, but which are not listed in Table A-2, the exempt material activity concentration and exempt consignment activity values contained in Table A-3 may be used. Otherwise, the licensee shall obtain prior U.S. NRC approval of the exempt material activity concentration and exempt consignment activity values for radionuclides not listed in Table A-2, before shipping the material. The licensee shall submit the requests for prior approval described in this Subsection to the U.S. NRC, in accordance with 10 CFR 71.1.

D.In the calculations of A1 and A2 for a radionuclide not in Table A-1, a single radioactive decay chain, in which radionuclides are present in their naturally-occurring proportions, and in which no daughter radionuclide has a half-life either longer than 10 days, or longer than that of the parent radionuclide, shall be considered as a single

radionuclide, and the activity to be taken into account, and

Louisiana Register   Vol. 34, No. 10   October 20, 2008

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