[Federal Register Volume 61, Number 110 (Thursday, June 6, 1996)]
[Rules and Regulations]
[Pages 28723-28725]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-14045]



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NUCLEAR REGULATORY COMMISSION

10 CFR Part 71

RIN 3150--AC41


Compatibility With the International Atomic Energy Agency; 
Correction

AGENCY: Nuclear Regulatory Commission.

ACTION: Correcting amendments.

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[[Page 28724]]

SUMMARY: This document presents corrections to a final rule that was 
published September 28, 1995 (60 FR 50248). This action is necessary to 
correct printing errors in three tables, an inadvertent error in an 
equation, an incorrect cross-reference, and the inadvertent use of a 
specialized term.

EFFECTIVE DATE: The final rule became effective April 1, 1996.

FOR FURTHER INFORMATION CONTACT: John R. Cook, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, Telephone (301) 415-8521.

SUPPLEMENTARY INFORMATION: On September 28, 1995 (60 FR 50248), the NRC 
published a final rule that revised NRC regulations in 10 CFR Part 71 
governing the transportation of radioactive material, to make them 
compatible with those of the International Atomic Energy Agency.
    This document corrects the use of a specialized term in paragraphs 
(2)(ii) and (3)(i) of the definition of Low Specific Activity (LSA) 
material in 10 CFR 71.4. This document also corrects Tables A-2 and A-3 
of Appendix A to Part 71 to remove an extra ``x'' in the presentation 
of exponents throughout the tables and the isotope of uranium 
referenced in footnote 1 to Table A-3.
    In addition, this document corrects a typographical error in the 
Minimum Transport Index equation in 10 CFR 71.18, an incorrect cross-
reference in 10 CFR 71.55, and a number of typographical errors in 
Table A-1 of Appendix A to Part 71.
    Each of the errors being corrected in this document was 
inadvertently included in the final rule for publication in the Federal 
Register.

List of Subjects in 10 CFR Part 71

    Criminal penalties, Hazardous materials transportation, Nuclear 
materials, Packaging and containers, Reporting and recordkeeping 
requirements.

    Accordingly, 10 CFR Part 71 is corrected by making the following 
correcting amendments:

PART 71--PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL

    1. The authority citation for Part 71 continues to read as follows:

    Authority: Secs. 53, 57, 62, 63, 81, 161, 182, 183, 68 Stat. 
930, 932, 933, 935, 948, 953, 954, as amended, Sec. 1701, 106 Stat. 
2951, 2952, 2953 (42 U.S.C. 2073, 2077, 2092, 2093, 2111, 2201, 
2232, 2233, 2297f); Secs. 201, as amended, 202, 206, 88 Stat. 1242, 
as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).

    Section 71.97 also issued under Sec. 301, Pub. L. 96-295, 94 Stat. 
789-790.
    2. In 10 CFR 71.4, paragraphs (2)(ii) and (3)(i) of the definition 
of Low Specific Activity (LSA) material are revised to read as follows:


Sec. 71.4  Definitions.

* * * * *
    Low Specific Activity (LSA) material. * * *
    (2) * * *
    (ii) Material in which the radioactive material is distributed 
throughout, and the average specific activity does not exceed 10<SUP>-4 
A<INF>2/g for solids and gases, and 10<SUP>-5 A<INF>2/g for liquids.
    (3) * * *
    (i) The radioactive material is distributed throughout a solid or a 
collection of solid objects, or is essentially uniformly distributed in 
a solid compact binding agent (such as concrete, bitumen, ceramic, 
etc.); and
* * * * *


Sec. 71.18  [Amended]

    3. In 10 CFR 71.18(d)(1), the equation for the Minimum 
Transportation Index is revised to read as follows:
[GRAPHIC] [TIFF OMITTED] TR06JN96.011

Sec. 71.55  [Amended]

    4. In 10 CFR 71.55(d)(3), the cross-reference to 
``Sec. 71.59(b)(1)'' is revised to read ``10 CFR 71.59(a)(1).''

Appendix A to Part 71  [Amended]

    5. Table A-1 of Appendix A to Part 71 is amended as follows:
    a. For the entry ``Ag-110m,'' Column (TBq/g) is revised to read 
``1.8 x 10<SUP>2.''
    b. For the entry ``Am-242m,'' Column (Ci/g) is revised to read 
``1.0 x 10<SUP>1.''
    c. For the entry ``Ar-39,'' Column (TBq/g) is revised to read 
``1.3.''
    d. For the entry ``Br-82,'' Column A<INF>1 (Ci) is revised to read 
``10.8.''
    e. For the entry ``C-11,'' Column A<INF>1 (Ci) is revised to read 
``27.''
    f. For the entry ``Cd-113m,'' Column (TBq/g) is revised to read 
``8.3.''
    g. For the entry ``Cm-244,'' Column A<INF>1 (Ci) is revised to read 
``108'' and Column (Ci/g) is revised to read ``8.1 x 10<SUP>1.''
    h. For the entry ``Es-253,'' Column A<INF>1 (TBq) is revised to 
read ``200,'' Column A<INF>1 (Ci) is revised to read ``5400,'' Column 
A<INF>2 (TBq) is revised to read ``2 x 10<SUP>-2,'' and Column A<INF>2 
(Ci) is revised to read ``5.41 x 10<SUP>-1.''
    i. For the entry ``Eu-150,'' Column (Ci/g) is revised to read 
``1.6 x 10<SUP>6.''
    j. For the entry ``Eu-155,'' Column (Ci/g) is revised to read 
``4.9 x 10<SUP>2.''
    k. For the entry ``F-18,'' Column (TBq/g) is revised to read 
``3.5 x 10<SUP>6.''
    l. For the entry ``Fe-59,'' Column (Ci/g) is revised to read 
``5.0 x 10<SUP>4.''
    m. For the entry ``Fm-257,'' Column A<INF>1 (TBq) is revised to 
read ``10,'' Column A<INF>1 (Ci) is revised to read ``270,'' Column 
A<INF>2 (TBq) is revised to read ``8 x 10<SUP>-3,'' and Column A<INF>2 
(Ci) is revised to read ``2.16 x 10<SUP>-1.''
    n. For the entry ``Gd-148,'' Column (TBq/g) is revised to read 
``1.2'' and Column (Ci/g) is revised to read ``3.2 x 10<SUP>1.''
    o. The entry for MFP is corrected to read ``For mixed fission 
products, use formula for mixtures or table A-2.''
    p. For the entry ``Pt-197m,'' Column (TBq/g) is revised to read 
``3.7 x 10<SUP>5.''
    5. In Appendix A to Part 71, Tables A-2 and A-3 are revised to read 
as follows:

Appendix A to Part 71--Determination of A<INF>1 and A<INF>2

* * * * *

                                    Table A-2.--General Values for A<INF>1 and A<INF>2                                    
----------------------------------------------------------------------------------------------------------------
                                                                     A<INF>1                             A<INF>2          
                           Contents                            -------------     (Ci)    -----------------------
                                                                   (TBq)                     (TBq)       (Ci)   
----------------------------------------------------------------------------------------------------------------
Only beta- or gamma-emitting nuclides are known to be present.         0.2          5          0.02    0.5      

[[Page 28725]]

                                                                                                                
Alpha-emitting nuclides are known to be present, or no                                                          
 relevant data are available..................................         0.10         2.70      2x10<SUP>-5   5.41x10<SUP>-4
----------------------------------------------------------------------------------------------------------------



           Table A-3.--Activity-mass Relationships for Uranium          
------------------------------------------------------------------------
                                                Specific Activity       
Uranium Enrichment<SUP>1 wt % U-235 present ---------------------------------
                                             TBq/g             Ci/g     
------------------------------------------------------------------------
 0.45.................................       1.8 x 10<SUP>-8       5.0 x 10<SUP>-7
 0.72.................................       2.6 x 10<SUP>-8       7.1 x 10<SUP>-7
 1.0..................................       2.8 x 10<SUP>-8       7.6 x 10<SUP>-7
 1.5..................................       3.7 x 10<SUP>-8       1.0 x 10<SUP>-6
 5.0..................................       1.0 x 10<SUP>-7       2.7 x 10<SUP>-6
 10.0.................................       1.8 x 10<SUP>-7       4.8 x 10<SUP>-6
 20.0.................................       3.7 x 10<SUP>-7       1.0 x 10<SUP>-5
 35.0.................................       7.4 x 10<SUP>-7       2.0 x 10<SUP>-5
 50.0.................................       9.3 x 10<SUP>-7       2.5 x 10<SUP>-5
 90.0.................................       2.2 x 10<SUP>-6       5.8 x 10<SUP>-5
 93.0.................................       2.6 x 10<SUP>-6       7.0 x 10<SUP>-5
 95.0.................................       3.4 x 10<SUP>-6       9.1 x 10<SUP>-5 
------------------------------------------------------------------------
\1\The figures for uranium include representative values for the        
  activity of the uranium-234 that is concentrated during the enrichment
  process.                                                              

    Dated at Rockville, MD this 29th day of May 1996.

    For the Nuclear Regulatory Commission.
James M. Taylor,
Executive Director for Operations.
[FR Doc. 96-14045 Filed 6-5-96; 8:45 am]
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