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PA Bulletin, Doc. No. 98-287e

[28 Pa.B. 881]

[Continued from previous Web Page]

NOTIFICATION

§ 226.51.  Notification of incidents, abandonment and lost sources.

   

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   (b)  The licensee shall immediately notify the Department by telephone and subsequently by confirming letter if the licensee knows or has reason to believe that radioactive material has been lost in or to an underground [potable] fresh water source. The notice shall designate the well location and shall describe the [magniture] magnitude and extent of loss of radioactive material, [access] assess the consequences of the loss and explain efforts planned or being taken to mitigate these consequences.

   (c)  If a sealed source or device containing radioactive material is lodged downhole, the licensee shall:

   (1)  Monitor at the surface for the presence of radioactive contamination with a radiation survey instrument or logging tool during logging tool recovery operations, as required under § 226.41 (relating to radiation surveys and contamination control).

   (2)  Notify the Department immediately by telephone if radioactive contamination is detected at the surface or if the source appears to be damaged, as required under § 226.41.

   

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   (e)  If a sealed source containing radioactive material is abandoned downhole, the licensee shall provide a permanent plaque [--an example of a suggested plaque is shown in Appendix B--] for posting the well or well-bore. The plaque shall:

   

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   (2)  Contain the following information engraved on its face:

   

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   (viii)  An appropriate warning, depending on the specific circumstances of the abandonment. Appropriate warnings may include:

   

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   (C)  ''Do not re-enter the hole,'' followed by the words ''before contacting the Pennsylvania Department of Environmental [Resources] Protection.''

   (3)  Be at least 7 inches (17cm) square and 1/8-inch (3mm) thick.

[APPENDIX B] (Reserved)

   (Editor's Note:  As part of this proposal, the Board is proposing to delete Appendix B (relating to example of plaque for identifying wells containing radioactive material abandoned downhole) which appears at 25 Pa. Code page 226-15, serial page (203991).)

CHAPTER 230.  PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL

Subchapter A.  SCOPE AND DEFINITIONS

§ 230.2.  Definitions.

   The following words and terms, when used in this chapter, have the following meanings, unless the context clearly indicates otherwise:

   

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   A2--The maximum activity of radioactive material, other than special form, [radioactive] LSA and SCO material, permitted in a Type A package. These values are either listed in Appendix A, Table I (relating to packaging and transportation of radioactive materials) or may be derived in accordance with the procedure prescribed in Appendix A.

   

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   [Closed transport vehicle--A transport vehicle equipped with a securely attached exterior enclosure that during normal transportation restricts the access of unauthorized persons to the cargo space containing the radioactive material. The enclosure may be temporary or permanent, but shall limit access from the top, sides and ends. In the case of packaged materials, the enclosure may be of the see-through type.]

   Containment system--The assembly of components of the packaging intended to retain the radioactive material during transport.

   Conveyance--Any of the following:

   (i)  For transport by public highway or rail, transport vehicle or large freight container.

   (ii)  For transport by water, vessel or hold, compartment or defined deck area of a vessel including transport vehicle on board the vessel.

   (iii)  For transport by air, any aircraft.

   Exclusive use--The sole use of a conveyance by a single consignor and for which initial, intermediate and final loading and unloading are carried out in accordance with the direction of the consignor or consignee. [The term is used interchangeably with the terms ''sole use'' or ''full load'' in other regulations, such as 49 CFR (relating to transportation).] The consignor and the carrier shall ensure that any loading or unloading is performed by personnel having radiological training and resources appropriate for safe handling of the consignment. The consignor shall issue specific instructions, in writing, for maintenance of exclusive use shipment controls, and include them with the shipping paper information provided to the carrier by the consignor.

   Fissile material--[Special nuclear material consisting of or containing one or more fissile radionuclides. Fissile radionuclides are plutonium] Plutonium-238, plutonium-239, plutonium-241, uranium-233, [and] uranium-235 or a combination of these radionuclides. The term does not include unirradiated natural uranium [or] and depleted uranium, and natural uranium or depleted uranium that has been irradiated in thermal reactors only. Department jurisdiction extends only to special nuclear material in quantities not sufficient to form a critical mass as defined in Chapter 215 (relating to general provisions).

   [(i)  Fissile Class I--A package which may be transported in unlimited numbers and in any arrangement, and which requires no nuclear criticality safety controls during transportation. A transport index is not assigned for purposes of nuclear criticality safety but may be required because of external radiation levels.

   (ii)  Fissile Class II--A package which may be transported together with other packages in any arrangement but, for criticality control, in numbers which do not exceed an aggregate transport index of 50. These shipments require no other nuclear criticality safety control during transportation. Individual packages may have a transport index not less than 0.1 and not more than 10.

   Fissile material package--A fissile material packaging together with its fissile contents as presented for transport.]

   

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   Low specific activity material--[Includes one or more of the following:

   (i)  Uranium or thorium ores and physical or chemical concentrates of those ores.

   (ii)  Unirradiated natural or depleted uranium or unirradiated natural thorium.

   (iii)  Tritium oxide in aqueous solutions provided the concentration does not exceed 5.0 millicuries (185 MBq) per milliliter.

   (iv)  Material in which the radioactivity is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed one of the following:

   (A)  0.0001 millicurie (3.7 kBq) of radionuclides for which the A2 quantity in Appendix A of this part is not more than 0.05 curie (1.85 GBq).

   (B)  0.005 millicurie (185 kBq) of radionuclides for which the A2 quantity in Appendix A of this part is more than 0.05 curie (1.85 GBq) but not more than 1 curie (37 GBq).

   (C)  0.3 millicurie (11.1 MBq) of radionuclides for which the A2 quantity in Appendix A of this part is more than 1 curie (37 GBq).

   (v)  Objects of nonradioactive material externally contaminated with radioactive material, if the radioactive material is not readily dispersible, and the surface contamination, when averaged over an area of 1 square meter, does not exceed 0.0001 millicurie per square centimeter (3.7 kBq/cm2) of radionuclides for which the A2 quantity in Appendix A is not more than 0.05 curie (1.85 GBq) or 0.001 millicurie per square centimeter (37 kBq/cm2) for other radionuclides.] Radioactive material with limited specific activity that satisfies the descriptions and limits as follows. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material shall be in one of three groups:

   (i)  LSA-I is any of the following:

   (A)  Ores containing only naturally occurring radionuclides, (for example, uranium, thorium) and uranium or thorium concentrates of these ores.

   (B)  Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures.

   (C)  Radioactive material, other than fissile material, for which the A2 value is unlimited.

   (D)  Mill tailings, contaminated earth, concrete, rubble, other debris and activated material in which the radioactive material is essentially uniformly distributed, and the average specific activity does not exceed 10-6 A2/g.

   (ii)  LSA-II is any of the following:

   (A)  Water with tritium concentration up to 0.8 TBq/liter (20.0 ci/liter).

   (B)  Material in which the radioactive material is distributed throughout, and the average specific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for liquids.

   (iii)  LSA-III solids (for example, consolidated wastes, activated materials) in which all of the following are met:

   (A)  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, and so forth).

   (B)  The radioactive material is relatively insoluble, or it is intrinsically contained in a relatvely insoluble material, so that, even under loss of packaging, the loss of radioactive material per package by leaching, when placed in water for 7 days, would not exceed 0.1 A2.

   (C)  The average specific activity of the solid does not exceed 2,000 A2/g.

   Low toxicity alpha emitters--Natural uranium, depleted uranium, natural thorium; uranium-235, uranium-238, thorium-232, thorium-228 or thorium-230 when contained in ores or physical or chemical contrates or tailings; or alpha emitters with a half-life of less than 10 days.

   Maximum normal operating pressure--The maximum gauge pressure that would develop in the containment system in 1 year under the heat condition specified in 10 CFR 71.71(c)(1) (relating to normal conditions of transport) in the absence of venting, external cooling by an ancillary system, or operational controls during transport.

   Natural thorium--Thorium with the naturally occurring distribution of thorium isotopes--essentially 100 weight percent thorium-232.

   

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   Surface contaminated object--A solid object that itself is not classed as radioactive material, but which has radioactive material distributed on any of its surfaces. SCO shall be in one of two groups with surface activity not exceding the following limits:

   (i)  SCO-1--A solid object to which all of the following conditions apply:

   (a)  The nonfixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed 4 Bq/cm2 (10-4 µC/cm2) for beta and gamma and low toxicity alpha emitters, or 0.4 Bq/cm2 (10-5 µCi/cm2) for all other alpha emitters.

   (B)  The fixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed 4 x 104 Bq/cm2 (1µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 4 x 1033 Bq/cm2 (0.1 µCi/cm2) for all other alpha emitters.

   (c)  The nonfixed contamination plus the fixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed does not exceed 4 x 104 Bq/cm2 (1 µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 4 x 103 Bq/cm2 (0.1 µCi/cm2) for all other alpha emitters.

   (ii)  SCO-2--A solid object on which the limits FRO SCO-1 are exceeded and on which:

   (a)  The nonfixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed 400 Bq/cm2 (10-2 µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 40 Bq/cm2 (10-3 µCi/cm2) for all other alpha emitters.

   (B)  The fixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed 8 x 105 Bq/cm2 (20 µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 8 x 104 Bq/cm2 (2 µCi/cm2) for all other alpha emitters.

   (c)  The nonfixed contamination plus the fixed contamination on the accessible surface averaged over 300 cm2--or the area of the surface if less than 300 cm2--does not exceed 8 x 105 Bq/cm2 (20 µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 8 x 104 Bq/cm2 (2 µCi/cm2) for all other alpha emitters.

   

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   Transport index--The dimensionless number, rounded up to the [first decimal place] next tenth, placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. For nonfissile material packages, the transport index is the number expressing the maximum radiation level in mrem per hour at 1 meter from the external surface of the package or the maximum radiation level in millisievert per hour at 1 meter from the external surface of the package multiplied by 100.

   

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   Uranium (natural, depleted, enriched)--One of the following:

   (i)  Natural uranium--Uranium with the naturally occurring distribution of uranium isotopes--approximately 0.711 weight percent uranium-235, and the remainder by weight essentially.

   (ii)  Depleted uranium--Urainium containing less uranium-235 than the naturally occurring distribution of isotopes.

   (iii)  Enriched uranium--Uranium containing more uranium-235 than the naturally occurring distribution of uranium isotopes.

Subchapter B.  GENERAL

§ 230.12.  Exemptions.

   

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   (c)  With the exception of §§ 230.13 and 230.42 (relating to transportation of licensed material; and preliminary determinations), a licensee is exempt from this chapter, with respect to shipment or carriage of one or more of the following:

   

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   (3)  A package in which only the radioactive material is LSA material or SCO, if the external level at 3 meters from the unshielded material or objects does not exceed 10 mSv/hr (1 rem/hr).

   (d)  A licensee is exempt from the requirements of this chapter, other than §§ 230.13 and 230.44 (relating to transportation of licensed material; and air transport of plutonium), with respect to shipment or carriage of LSA material in group LSA-1, or SCO in group SCO-1.

Subchapter C.  USE OF APPROVED PACKAGES

   (Editor's Note:  The Department is proposing to delete §§ 230.25 and 230.26 (relating to Type A Fissile Class II package; and restricted, Fissile Class II package) as they currently appear in the Pennsylvania Code at pages 230-9--230-11 (serial pages (204181)--(204183).

§ 230.25.  (Reserved).

§ 230.26.  (Reserved).

Subchapter D.  OPERATING CONTROLS AND PROCEDURES

§ 230.41.  [Fissile material: assumptions as to unknown properties] Applicability of operating controls and procedures.

   [When the isotopic abundance, mass, concentration, degree of irradiation, degree of moderation or other pertinent property of fissile material in a package is not known, the licensee shall package the fissile material as if the unknown properties had credible values that would cause the maximum nuclear reactivity.] A licensee subject to this chapter, who, under a general or specific license, transports licensed material or delivers licensed material to a carrier for transport, shall comply with this subchapter, Subchapter B and Subchapter E (relating to general; and quality assurances).

§ 230.42.  Preliminary determinations.

   Prior to the first use of packaging for the shipment of radioactive material the licensee shall do the following:

   

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   (2)  Test the containment system at an internal pressure at least 50% higher than the maximum normal operating pressure to verify the capability of that system to maintain its structural integrity at that pressure, [where] if the maximum normal operating pressure will exceed [34.3] 35 kilopascal (5 psi) gauge.

   

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§ 230.48.  Opening instructions.

   Before delivery of a package to a carrier for transport, the licensee shall ensure that special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignee's use under § 219.162(e) (relating to procedures for receiving and opening packages).

APPENDIX A

DETERMINATION OF A1 AND A2

   [I.  Single Radionuclides.

   1.  For a single radionuclide of known identity, the values of A1 and A2 are taken from Table I if listed there. The values A1 and A2 in Table I are also applicable for the radionuclide contained in (alpha,n) or (gamma,n) neutron sources.

   2.  For any single radionuclide whose identity is known but which is not listed in Table I, the value of A1 and A2 are determined according to the following procedure:

   (a)  If the radionuclide emits only one type of radiation A1 is determined according to the appropriate formula in paragraphs (1) through (4). For radionuclides emitting different kinds of radiation, A1 is the most restrictive value of those determined for each kind of radiation. However, in either case, A1 is restricted to a maximum of 1,000 curies (37 TBq). If a parent nuclide decays into a shorter lived daughter with a half-life not greater than 10 days, A1 is calculated for both the parent and the daughter, and the more limiting of the two values is assigned to the parent nuclide.

   (1)  For gamma emitters, A1 is determined by the expression:

   A1 = 9 curies/|gg

where |gg is the gamma-ray constant, corresponding to the dose in roentgens per curie-hour at 1 meter, and the number 9 results from the choice of 1 rem per hour at a distance of 3 meters as the reference dose-equivalent rate.

   (2)  For x-ray emitters, A1 is determined by the atomic number of the nuclide:

   for Z <= 55, A1 = 1,000 Ci (37 TBq); and

   for Z > 55, A1 = 200 Ci (7.4 TBq)

where Z is the atomic number of the nuclide.

   (3)  For beta emitters, A1 is determined by the maximum beta energy (Emax) according to Table II; and

   (4)  For alpha emitters, A1 is determined by the expression:

   A1 = 1,000 A3

where A3 is the value listed in Table III;

   (b)  A2 is the more restrictive of the following two values:

   (1)  The corresponding A1; and

   (2)  The value A3 obtained from Table III.

   3.  For any single radionuclide whose identity is unknown, the value of A1 is taken to be 2 Ci (74 GBq) and the value of A2 is taken to be 0.002 Ci (74 MBq). However, if the atomic number of the radionuclide is known to be less than 82, the value of A1 is taken to be 10 Ci (370 GBq) and the value of A2 is taken to be 0.4 Ci (14.8 GBq).] 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) figure. The curie values are expressed to three significant figures to assure that the difference in the TBq and Ci quantities is 1/10 of 1% or less. Where values of A1 or A2 are unlimited, it is for radiation control purposes only. For nuclear criticality safety, some materials are subject to controls placed on fissile material.

   II.  [Mixtures of Radionuclides, Including Radioactive Decay Chains.

   1.  For mixed fission products, the activity limit may be assumed if a detailed analysis of the mixture is not carried out,

   A1 = 10 Ci (370 GBq)

   A2 = 0.4 Ci (14.8 GBq)

   2.  A single radioactive decay chain is considered to be a single radionuclide when the radionuclides are present in their naturally occurring proportions and no daughter nuclide has a half-life either longer than 10 days or longer than that of the parent nuclide. The activity to be taken into account and the A1 or A2 value from Table I to be applied are those corresponding to the parent nuclide of that chain. When calculating A1 or A2 values, radiation emitted by daughters must be considered. However, in the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than 10 days or greater than that of the parent nuclide, the parent and daughter nuclides are considered to be mixtures of different nuclides.

   3.  In the case of a mixture of different radionuclides, where the identity and activity of each radionuclide are known, the permissible activity of each radionuclide R1, R2 . . . Rn is such that F1 + F2 + . . . Fn is not greater than unity, where:

                  F1 = Total activity of R1/ Ai(R1)

                  F2 = Total activity of R2/Ai(R2)

                  Fn = Total activity of Rn/Ai(Rn) and

   Ai (R1, R2 . . . Rn) is the value of A1 or A2 as appropriate for the nuclide R1, R2 . . . Rn.

   4.  When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the formula given in paragraph 3. is applied to establish the values of A1 or A2 as appropriate. All the radionuclides whose individual activities are not known (their total activity will, however, be known) are classed in a single group and the most restrictive value of A1 and A2 applicable to any one of them is used as the value of A1 or A2 in the denominator of the fraction.

   5.  Where the identity of each radionuclide is known but the individual activity of none of the radionuclides is known, the most restrictive value of A1 or A2 applicable to any one of the radionuclides present is adopted as the applicable value.

   6.  When the identity of none of the nuclides is known, the value of A1 is taken to be 2 Ci (74 GBq) and the value of A2 is taken to be 0.002 Ci (74 MBq). However, if alpha emitters are known to be absent, the value of A2 is taken to be 0.4 Ci (14.8 GBq).] For individual radionuclides whose identities are known, but which are not listed in Table A-1, the determination of the values of A1 and A2 requires Department approval, except that the values of A1 and A2 in Table A-2 may be used without Department approval.

   III.  In the calculations of A1 and A2 for a radionuclide not in Table A-1, a single radioactive decay chain, in which no daughter nuclides a half-life either longer than 10 days, or longer than that of the parent nuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A1 or A2 value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than 10 days, or greater than that of the parent nuclide, the parent and those daughter nuclides shall be considered mixtures of different nuclides.

   IV.  For mixtures of radionuclides whose identities and respective activities are known, the following conditions apply:

   (a)  For special form radioactive material, the maximum quantity transported in a Type A package:

   SUMI B(i)/A1(i) less than or equal to 1

   (b)  For normal form radioactive material, the maximum quantity transported in a Type A package:

   SUMI B(i)/A2(i) less than or equal to 1

where B(i) is the activity of radionuclide I and A1(i) and A2(i) are the A1 and A2 values for radionuclide I, respectively.

   Alternatively, an A1 value for mixtures of special form material may be determined as follows:

   A1 for mixture = 1/(SUMI F(i)/A1(i))

where F(i) is the fraction of activity of nuclide I in the mixture and A1(i) is the appropriate A1 value for nuclide I.

   An A2 value for mixtures of normal form material may be determined as follows:

   A2 for mixture = 1/(SUMI F(i)/A2(i)

where F(i) is the fraction of activity of nuclide I in the mixture and A2(i) is the appropriate A2 value for nuclide I.

   V.  When the identity of each radionuclide is known, but the individual activities of some radionuclides are not known, the radionuclides may be grouped and the lowest A1 or A2 value, as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph IV. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest A1 or A2 values for the alpha emitters and beta/gamma emitters.

   (Editor's Note:  The Department is proposing to delete Tables I--IV as they currently appear in the Pennsylvania Code pages 230-21--230-30 (serial pages (204193)--(204202)) and replace them with new Tables A-1 and A-2).

TABLE A-1

A1 and A2 Values for Radionuclides

(See Footnotes at End of Table)

   Note:  Some of the values in Table A-1 are presented in the Computer "E" notation. In this notation a value of 6E-02 represents a value of 6 X 10-2 or 0.06, 6E+2 represents 6 X 102 or 600, and 6E+0 represents 6 X 100 or 6.

Symbol ofElement andA1A1A2A2Specific activity
radionuclideatomic number(TBq)(Ci)(TBq)(Ci)(TBq/g)(Ci/g)
Ac-225Actinium (89)0.616.21E-20.2702.1E+35.8E+4
Ac-2274010802E-55.41E-42.77.2E+1
Ac-2280.616.20.410.88.4E+42.2E+6
Ag-105Silver (47)254.1254.11.1E+33.0E+4
Ag-108m0.616.20.616.29.7E-12.6E1
Ag-110m0.410.80.410.81.8E+24.7E+3
Ag-1110.616.20.513.55.8E+31.9E+5
Al-26Aluminum (13)0.410.80.410.87.0E-41.9E-2
Am-241Americium (95)254.12E-45.41E-31.3E-13.4
Am-242m254.12E-45.41E-33.6E-11.0E+1
Am-243254.12E-45.41E-37.4E-32.0E-1
Ar-37Argon (18)4010804010803.7E+39.9e+4
Ar-3920541205411.33.4E+1
Ar-410.616.20.616.21.5E+64.2E+7
Ar-420.25.410.25.419.62.6E+2
As-72Arsenic (33)0.25.410.25.416.2E+41.7E+6
As-734010804010808.2E+22.2E+4
As-74127.00.513.53.7E+39.9E+4
As-760.25.410.25.415.8E+41.6E+6
As-77205410.513.53.9E+41.0E+6
At-211Astatine (85)30811254.17.6E+42.1E+6
Au-193Gold (79)616261623.4E+49.2E+5
Au-194127.0127.01.5E+44.1E+5
Au-19510270102701.4E+23.7E+3
Au-196254.1254.14.0E+31.1E+5
Au-198381.10.513.59.0E+32.4E+5
Au-199102700.924.37.7E+32.1E+5
Ba-131Barium (56)254.1254.13.1E+38.4E+4
Ba-133m102700.924.32.2E+46.1E+5
Ba-1400.410.80.410.82.7E+37.3E+4
Be-7Beryllium (4)20541205411.3E+43.5E+5
Be-10205410.513.58.3E-42.2E-2
Bi-205Bismuth (83)0.616.20.616.21.5E-34.2E+4
Bi-2060.38.110.38.113.8E+31.0E+5
Bi-2070.718.90.718.91.95.2E+1
Bi-210m0.38.113E-20.8112.1E-55.7e-4
Bi-2120.38.110.38.115.4E+51.5E+7
Bk-247Berkelium (97)254.12E-45.41E-33.8E-21.0
Bk-2494010808E-22.166.1E+11.6E+3
Br-76Bromine (76)0.38.110.38.119.4E++42.5E+6
Br-77381.1381.12.4E+47.1E+5
Br-820.410.80.410.84.0E+41.1E+6
C-11Carbon (6)1270.513.53.1E+78.4E+8
C-14401080254.11.6E-14.5
Ca-41Calcium (20)4010804010803.1E-38.5E-2
Ca-454010800.924.36.6E+21.8E+4
Ca-470.924.30.513.52.3E+46.1E+5
Cd-109Cadmium (48)4010801279.6E+12.6E+3
Cd-113m205419E-22.438.32.2E+2
Cd-115m0.38.110.38.119.4E+22.5E+4
Cd-11541080.513.51.9E+45.1E+5
Ce-139Cerium (58)616261622.5E+26.8E+3
Ce-141102700.513.51.1E+32.8E+4
Ce-1430.616.20.513.52.5E+46.6E+5
Ce-1440.25.410.25.411.2E+23.3E+3
Cf-248Californium (98)308113E-38.11E-25.8E+11.6E+3
Cf-249254.12E-45.41E-31.5E-14.1
Cf-25051355E-41.35E-24.01.1E+2
Cf-251254.12E-45.41E-35.9E-21.6
Cf-2520.12.701E-32.70E-22.0E+15.4E+2
Cf-2534010806E-21.621.1E+32.9E+4
Cf-2543E-18.11E-26E-41.62E-23.1E+28.5E+3
Cl-36Chlorine (36)205410.513.51.2E-33.3E-2
Cl-380.25.410.25.414.9E+61.3E+8
Cm-240Curium (96)4010802E-20.5417.5E+22.0E+4
Cm-241254.10.9 24.36.1E+21.7E+4
Cm-2424010801E-20.2701.2E+23.3E+3
Cm-243381.13E-48.11E-31.95.2E+1
Cm-24441084E-41.08E-23.08.1E+1
Cm-245254.12E-45.41E-36.4E-31.7E-1
Cm-246254.12E-45.41E-31.1E-23.1E-1
Cm-247254.12E-45.41E-33.4E-69.3E-5
Cm-2484E-21.085E-31.35E-31.6E-44.2E-3
Co-55Cobalt (27)0.513.50.513.51.1E+53.1E+6
Co-560.38.110.38.111.1E+33.0E+4
Co-57821682163.1E+28.4E+3
Co-58m4010804010802.2E+55.9E+6
Co-58127.0127.01.2E+33.2E+4
Co-600.410.80.410.84.2E+11.1E+3
Cr-51Chromium (24)30811308113.4E+39.2E+4
Cs-129Cesium (55)410841082.8E+47.6E+5
Cs-1314010804010803.8E+31.0E+5
Cs-132127.0127.05.7E+31.5E+5
Cs-134m40108092433.0E+58.0E+6
Cs-1340.616.20.513.54.8E+11.3E+3
Cs-1354010800.924.34.3E-51.2E-2
Cs-1360.513.50.513.52.7E+37.3E+4
Cs-137254.10.513.53.28.7E+1
Cu-64Copper (29)51350.924.31.4E+53.9E+6
Cu-6792430.924.32.8E+47.6E+5
Dy-159Dysprosium (66)20541205412.1E+25.7E+3
Dy-1650.616.20.513.53.0E+58.2E+6
Dy-1660.38.110.38.118.6E+32.3E+5
Er-169Erbium (68)4010800.924.33.1E+38.3E+4
Er-1710.616.20.513.59.0E+42.4E+6
Es-253Einsteinium (99)(a)20054002E-25.41E-1
Es-254308113E-38.11E-2
Es-254m0.616.20.410.8
Es-255
Eu-147Europium (63)254.1254.11.4E+33.7E+4
Eu-1480.513.50.513.56.0E+21.6E+4
Eu-14920541205413.5E+29.4E+3
Eu-1500.718.90.718.96.1E+41.6E+6
Eu-152m0.616.20.513.58.2E+42.2E+6
Eu-1520.924.30.924.36.51.8E+2
Eu-1540.821.60.513.59.82.6E+2
Eu-15520541254.11.8E+14.9E+2
Eu-1560.616.20.513.52.0E+35.5E+4
F-18Fluorine (9)127.00.513.53.5E+69.5E+7
Fe-52Iron (26)0.25.410.25.412.7E+57.3E+6
Fe-554010804010808.8E+12.4E+3
Fe-590.821.60.821.61.8E+35.0E+4
Fe-604010800.25.417.4E-42.0E-2
Fm-255Fermium (100)(b)4010800.821.6
Fm-257102708E-321.6E-1
Ga-67Gallium(31)616261622.2E+46.0E+5
Ga-680.38.110.38.111.5E+64.1E+7
Ga-720.410.80.410.81.1E+53.1E+6
Gd-146Gadolinium (64)0.410.80.410.86.9E+21.9E+4
Gd-148381.13E-48.11E-31.23.2E+1
Gd-1531027051351.3E+23.5E+3
Gd-15941080.513.53.9E+41.1E+6
Ge-68Germanium (32)0.38.110.38.112.6E+27.1E+3
Ge-714010804010805.8E+31.6E+5
Ge-770.38.110.38.111.3E+53.6E+6
H-3Hydrogen (1) See T-Tritium
Hf-172Hafnium (72)0.513.50.38.114.1E+11.1E+3
Hf-175381.1381.13.9E+21.1E+4
Hf-181254.10.924.36.3E+21.7E+4
Hf-18241083E-20.8118.1E-62.2E-4
Hg-194Mercury (80)127.0127.01.3E-13.5
Hg-195m513551351.5E+44.0E+5
Hg-197m102700.924.32.5E+46.7E+5
Hg-19710270102709.2E+32.5E+5
Hg-20341080.924.35.1E+21.4E+4
Ho-163Holmium (67)4010804010802.77.6E-1
Ho-166m0.616.20.38.116.6E-21.8
Ho-1660.38.110.38.112.6E+47.0E+5
I-123Iodine (53)616261627.1E+41.9E+6
I-1240.924.30.924.39.3E+32.5E+5
I-12520541254.16.4E+21.7E+4
I-126254.10.924.32.9E+38.0E+4
I-129UnlimitedUnlimited6.5E-61.8E-4
I-131381.10.513.54.6E+31.2E+5
I-1320.410.80.410.83.8E+51.0E+7
I-1330.616.20.513.54.2E+41.1E+6
I-1340.38.110.38.119.9E+52.7E+7
I-1350.616.20.513.51.3E+53.5E+6
In-111Indium (49)254.1254.11.5E+44.2E+5
In-113m410841086.2E+51.7E+7
In-114m0.38.110.38.118.6E+22.3E+4
In-115m61620.924.32.2E+56.1E+6
Ir-189Iridium (77)10270102701.9E+35.2E+4
Ir-1900.718.90.718.92.3E+36.2E+4
Ir-192127.00.513.53.4E+29.2E+3
Ir-193m10270102702.4E+36.4E+4
Ir-1940.25.410.25.413.1E+48.4E+5
K-40Potassium (19)0.616.20.616.22.4E-76.4E-6
K-420.25.410.25.412.2E+56.0E+6
K-431.027.00.513.51.2E+53.3E+6
Kr-81Krypton (39)4010804010807.8E-42.1E-2
Kr-85m616261623.0E+58.2E+6
Kr-8520541102701.5E+13.9E+2
Kr-870.25.410.25.411.0E+62.8E+7
La-137Lanthanum (57)401080254.11.6E-34.4E-2
La-1400.410.80.410.82.1E+45.6E+5
Lu-172Lutetium (71)0.513.50.513.54.2E+31.1E+5
Lu-173821682165.6E+11.5E+3
Lu-174m2054182162.0E+25.3E+3
Lu-174821641082.3E+16.2E+2
Lu-177308110.924.34.1E+31.1E+5
MFPFor mixed fisson products,use formulas for mixtures in Table A-2
Mg-28Magnesium (12) 0.254.10.254.12.0E+55.4E+6
Mn-52Manganese (25)
Mn-53UnlimitedUnlimited6.8E-51.8E-3
Mn-54127.0127.02.9E+27.7E+3
Mn-560.25.410.25.418.0E+52.2E+7
Mo-93Molybdenum (42)40108071894.1E-21.1
Mo-990.616.20.513.5(c)1.8E+44.8E+5
N-13Nitrogen (7)0.616.20.513.55.4E+71.5E+9
Na-22Sodium (22)0.513.50.513.52.3E+26.3E+3
Na-240.25.410.25.413.2E+58.7E+6
Nb-92mNiobium (41)0.718.90.718.95.3E+31.4E+5
Nb-93m40108061628.82.4E+2
Nb-940.616.20.616.26.9E-31.9E-1
Nb-95127.0127.01.5E+33.9E+4
Nb-970.616.20.513.59.9E+52.7E+7
Nd-147Neodymium (60)41080.513.53.0E+38.1E+4
Nd-1490.616.20.513.54.5E+51.2E+7
Ni-59Nickel(28)4010804010803.0E-38.0E-2
Ni-63401080308112.15.7E+1
Ni-650.38.110.38.117.1E+51.9E+7
Np-235Neptunium(93)4010804010805.2E+11.4E+3
Np-23671891E-32.70E-24.7E-41.3E-2
Np-237254.12E-45.41E-32.5E-57.1E-4
Np-23961620.513.58.6E+32.3E+5
Os-185Osmium(76)127.0127.02.8E+27.5E+3
Os-191m4010804010804.6E+41.3E+6
Os-191102700.924.31.6E+34.4E+4
Os-1930.616.20.513.52.0E+45.3E+5
Os-1940.25.410.25.411.1E+13.1E+2
P-32Phosphorus(15)0.38.110.38.111.1E+42.9E+5
P-334010800.924.35.8E+31.6E+5
Pa-230Protactinium (91)254.10.12.701.2E+33.3E+4
Pa-2310.616.26E-51.62E-31.7E-34.7E-2
Pa-23351350.924.37.7E+22.1E+4
Pb-201Lead(82)127.0127.06.2E+41.7E+6
Pb-202401080254.11.4E-43.4E-3
Pb-203381.1381.11.1E+43.0E+5
Pb-205UnlimitedUnlimited4.5E-61.2E-4
Pb-2100.616.29E-30.2432.87.6E+1
Pb-2120.38.110.38.115.1E+41.4E+6
Pd-103Palladium(46)4010804010802.8E+37.5E+4
Pd-107UnlimitedUnlimited1.9E-55.1E-4
Pd-1090.616.20.513.57.9E+42.1E+6
Pm-143Promethium(61)381.1381.11.3E+23.4E+3
Pm-1440.616.20.616.29.2E+12.5E+3
Pm-1453081171895.21.4E+2
Pm-1474010800.924.33.4E+19.3E+2
Pm-148m0.513.50.513.57.9E+22.1E+4
Pm-1490.616.20.513.51.5E+44.0E+5
Pm-151381.10.513.52.7E+47.3E+5
Po-208Polonium(84)4010802E-20.5412.2E+15.9E+2
Po-2094010802E-20.5416.2E-11.7E+1
Po-2104010802E-20.5411.7E+24.5E+3
Pr-142Praseodymium(59)0.25.410.25.414.3E+41.2E+6
Pr-14341080.513.52.5E+36.7E+4
Pt-188Platinum(78)0.616.20.616.22.5E+36.8E+4
Pt-191381.1381.18.7E+32.4E+5
Pt-191m40108092435.8E+31.6E+5
Pt-1934010804010801.43.7E+1
Pt-195m10270254.16.2E+31.7E+5
Pt-197m102700.924.33.7E+51.0E+7
Pt-197205410.513.53.2E+48.7E+5
Pu-236Plutonium(94)71897E-41.89E-22.0E+15.3E+2
Pu-23720541205414.5E+21.2E+4
Pu-238254.12E-45.41E-36.3E-11.7E+1
Pu-239254.12E-45.41E-32.3E-36.2E-2
Pu-240254.12E-45.41E-38.4E-32.3E-1
Pu-2414010801E-20.2703.81.0E+2
Pu-242254.12E-45.41E-31.5E-43.9E-3
Pu-2440.38.112E-45.41E-36.7E-71.8E-5
Ra-223Radium(88)0.616.23E-20.8111.9E+35.1E+4
Ra-2240.38.116E-21.625.9E+31.6E+5
Ra-2250.616.22E-20.5411.5E+33.9E+4
Ra-2260.38.112E-20.5413.7E-21.0
Ra-2280.616.24E-21.081.0E+12.7E+2
Rb-81Rubidium(37)254.10.924.33.1E+58.4E+6
Rb-83254.1254.16.8E+21.8E+4
Rb-84127.00.924.31.8E+34.7E+4
Rb-860.38.110.38.113.0E+38.1E+4
Rb-87UnlimitedUnimited3.2E-98.6E-8
Rb(natural)UnlimitedUnlimited6.7E+61.8E+8
Re-183Rhenium(75)513551353.8E+21.0E+4
Re-184m381.1381.11.6E+24.3E+3
Re-184127.0127.06.9E+21.9E+4
Re-18641080.513.56.9E+31.9E+5
Re-187UnlimitedUnlimited1.4E-93.8E-8
Re-1880.25.410.25.413.6E+49.8E+5
Re-18941080.513.52.5E+46.8E+5
Re(natural)UnlimitedUnlimited2.4E-8
Rh-99Rhodium(45)254.1254.13.0E+38.2E+4
Rh-101410841084.1E+11.1E+3
Rh-102m254.10.924.32.3E+26.2E+3
Rh-1020.513.50.513.54.5E+11.2E+3
Rh-103m4010804010801.2E+63.3E+7
Rh-105102700.924.33.1E+48.4E+5
Rn-222Radon(86)0.25.414E-30.1085.7E+31.5E+5
Ru-97Ruthenium(44)410841081.7E+44.6E+5
Ru-103254.10.924.31.2E+33.2E+4
Ru-1050.616.20.513.52.5E+56.7E+6
Ru-1060.25.410.25.411.2E+23.3E+4
S-35Sulfur(16)401080254.11.6E+34.3E+4
Sb-122Antimony(51)0.38.110.38.111.5E+44.0E+5
Sb-1240.616.20.513.56.5E+21.7E+4
Sb-125254.10.924.33.9E+11.0E+3
Sb-1260.410.80.410.83.1E+38.4E+4
Sc-44Scandium(21)0.513.50.513.56.7E+51.8E+7
Sc-460.513.50.513.51.3E+33.4E+4
Sc-4792430.924.33.1E+48.3E+5
Sc-480.38.110.38.115.5E+41.5E+6
Se-75Selenium(34)381.1381.15.4E+21.5E+4
Se-79401080254.12.6E-37.0E-2
Si-31Silicon(14)0.616.20.513.51.4E+63.9E+7
Si-324010800.25.413.91.1E+2
Sm-145Samarium(62)20541205419.8E+12.6E+3
Sm-147UnlimitedUnlimited8.5E-12.3E+1
Sm-15140108041089.7E-12.6E+1
Sm-15341080.513.51.6E+44.4E+5
Sn-113Tin(50)410841083.7E+21.0E+4
Sn-117m9162254.13.0E+38.2E+4
Sn-119m4010804010801.4E+23.7E+3
Sn-121m4010800.924.32.05.4E+1
Sn-1230.616.20.513.53.0E+28.2E+3
Sn-1250.25.410.25.414.0E+31.1E+5
Sn-1260.38.110.38.111.0E-32.8E-2
Sr-82Strontium(38)0.25.410.25.412.3E+36.2E+4
Sr-85m513551351.2E+63.3E+7
Sr-85254.1254.18.8E+22.4E+4
Sr-87m381.1381.4.8E+51.3E+7
Sr-890.616.20.513.51.1E+32.9E+4
Sr-900.25.410.12.705.11.4E+2
Sr-910.38.110.38.111.3E+53.6E+6
Sr-920.821.60.513.54.7E+51.3E+7
TTritium(1)4010804010803.6E+29.7E+3
Ta-178Tantalum(73)127.0127.04.2E+61.1E+8
Ta-17930811308114.1E+11.1E+3
Ta-1820.821.60.513.52.3E+26.2E+3
Tb-157Terbium(65)401080102705.6E-11.5E+1
Tb-158127.00.718.95.6E-11.5E+1
Tb-1600.924.30.513.54.2E+21.1E+4
Tc-95mTechnetium(43)254.1254.18.3E+22.2E+4
Tc-96m0.410.80.410.81.4E+63.8E+7
Tc-960.410.80.410.81.2E+43.2E+5
Tc-97m4010804010805.6E+21.5E+4
Tc-97UnlimitedUnlimited5.2E-51.4E-3
Tc-980.718.90.718.93.2E-58.7E-4
Tc-99m821682161.9E+55.3E+6
Tc-994010800.924.36.3E-41.7E-2
Te-118Tellurium(52)0.25.410.25.416.8E+31.8E+5
Te-121m513551352.6E+27.0E+3
Te-121254.1254.12.4E+36.4E+4
Te-123m718971893.3E+28.9E+3
Te-125m3081192436.7E+21.8E+4
Te-127m205410.513.53.5E+29.4E+3
Te-127205410.513.59.8E+42.6E+6
Te-129m0.616.20.513.51.1E+33.0E+4
Te-1290.616.20.513.57.7E+52.1E+7
Te-131m0.718.90.513.53.0E+48.0E+5
Te-1320.410.80.410.81.1E+43.0E+5
Th-227Thorium(90)92431E-20.2701.1E+33.1E+4
Th-2280.38.114E-41.08E-23.0E+18.2E+2
Th-2290.38.113E-58.11E-47.9E-32.1E-1
Th-230254.12E-45.41E-37.6E-42.1E-2
Th-2314010800.924.32.0E+45.3E+5
Th-232UnlimitedUnlimited4.0E-91.1E-7
Th-2340.25.410.25.418.6E+22.3E+4
Th(natural)UnlimitedUnlimited8.1E-92.2E-7
Ti-44Titanium(22)0.513.50.25.416.41.7E+2
Tl-200Thallium(81)0.821.60.821.62.2E+46.0E+5
Tl-20110270102707.9E+32.1E+5
Tl-202254.1254.12.0E+35.3E+4
Tl-20441080.513.51.7E+14.6E+2
Tm-167Thulium(69)718971893.1E+38.5E+4
Tm-1680.821.60.821.63.1E+28.3E+3
Tm-17041080.513.52.2E+26.0E+3
Tm-171401080102704.0E+11.1E+3
U-230Uranium(92)4010801E-20.2701.0E+32.7E+4
U-232381.13E-48.11E-38.3E-12.2E+1
U-233102701E-32.70E-23.6E-49.7E-3
U-234102701E-32.70E-22.3E-46.2E-3
U-235UnlimitedUnlimited8.0E-82.2E-6
U-236102701E-32.7E-22.4E-66.5E-5
U-238UnlimitedUnlimited1.2E-83.4E-7
U(natural)UnlimitedUnlimited2.6E-87.1E-7
U(enriched 5% or less)UnlimitedUnlimited(See
Table A-e)
U(enriched more than 5%)102701E-32.7E-2(See
Table A-3)
U(depleted)UnlimitedUnlimited(See
Table A-3)
V-48Vanadium(23)0.38.110.38.116.3E+31.7E+5
V-494010804010803.0E+28.1E+3
W-178Tungsten(74)127.0127.01.3E+33.4E+4
W-18130811308112.2E+26.0E+3
W-1854010800.924.33.5E+29.4E+3
W-187254.10.513.52.6E+47.0E+5
W-1880.25.410.25.413.7E+21.0E+4
Xe-122Xenon(54)0.25.410.25.414.8E+41.3E+6
Xe-1230.25.410.25.414.4E+51.2E+7
Xe-127410841081.0E+32.8E+4
Xe-131m4010804010803.1E+38.4E+4
Xe-13320541205416.9E+31.9E+5
Xe-135410841089.5E+42.6E+6
Y-87Yttrium(39)254.1254.11.7E+44.5E+5
Y-880.410.80.410.85.2E+21.4E+4
Y-900.25.410.25.412.0E+45.4E+5
Y-91m254.1254.11.5E+64.2E+7
Y-910.38.110.38.119.1E+22.5E+4
Y-920.25.410.25.413.6E+59.6E+6
Y-930.25.410.25.411.2E+53.3E+6
Yb-169Ytterbium(70)381.1381.18.9E+22.4E+4
Yb-175308110.924.36.6E+31.8E+5
Zn-65Zinc(30)254.1254.13.0E+28.2E+3
Zn-69m254.10.513.51.2E+53.3E+6
Zn-6941080.513.51.8E+64.9E+7
Zr-88Zirconium(40)381.1381.16.6E+21.8E+4
Zr-934010800.25.419.3E-52.5E-3
Zr-95127.00.924.37.9E+22.1E+4
Zr-970.38.110.38.117.1E+41.9E+6

   (a)  International shipments of Einsteinium require multilateral approval of A1 and A2 values.

   (b)  International shipments of Fermium require multilateral approval of A1 and A2 values.

   (c)  20 Ci for Mo-99 for domestic use.

TABLE A-2

GENERAL VALUES FOR A1 AND A2

ContentsA1A2
(TBq)(Ci)(TBq)(Ci)
Only beta- or gamma-emitting nuclides are known to be present0.205.000.020.5
Alpha-emitting nuclides are known to be present, or no relevant data are available0.102.702x10-55.41x10-4

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