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Procedural Rules for DOE Nuclear Activities and Occupational Radiation Protection
Note: EPA no longer updates this information, but it may be useful as a reference or resource.
[Federal Register: August 10, 2006 (Volume 71, Number 154)]
[Proposed Rules]
[Page 45995-46025]
From the Federal Register Online via GPO Access [wais.access.gpo.gov]
[DOCID:fr10au06-15]
[[Page 45996]]
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DEPARTMENT OF ENERGY
10 CFR Parts 820 and 835
[Docket No. EH-RM-02-835]
RIN 1901-AA95
Procedural Rules for DOE Nuclear Activities and Occupational
Radiation Protection
AGENCY: Department of Energy.
ACTION: Proposed rule and opportunity for public comment.
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SUMMARY: The Department of Energy (DOE or the Department) proposes to
amend its Procedural Rules for DOE Nuclear Activities, and its
Occupational Radiation Protection requirements. The proposed amendments
to the Procedural Rules for DOE Nuclear Activities would update its
provisions to take into account the establishment of the National
Nuclear Security Administration (NNSA). The proposed amendments to the
Occupational Radiation Protection requirements would update its
provisions to take into account lessons learned since the initial
adoption of these regulations, input from the Defense Nuclear
Facilities Safety Board (DNFSB) and members of the public, new
recommendations from the International Commission on Radiological
Protection (ICRP), and the establishment of the NNSA.
DATES: Public comments on the proposed rule must be received on or
before October 10, 2006. A public hearing will be held on September 21,
2006 at the DOE Auditorium, located on 19901 Germantown Road,
Germantown, Maryland. The hearing will be held from 9 a.m. to 12 noon
and, if needed, from 1 p.m. to 4 p.m. All meeting attendees will be
required to show a photo identification to access the DOE Germantown
property and Auditorium. Motor vehicles will also be inspected when
entering the DOE property.
Requests to speak at the public hearing should be mailed to Mr.
Peter O'Connell, Office of Worker Protection Policy and Programs, U.S.
Department of Energy, 1000 Independence Avenue, SW., Washington, DC
20585. You may also e-mail your request to speak to
Peter.O'Connell@eh.doe.gov or telephone Mr. O'Connell at (301)
903-5641. Requests to speak must be received by September 7, 2006 for the
Germantown, Maryland hearing. Each presentation is limited to no more than
10 minutes to ensure that all persons have an opportunity to speak.
ADDRESSES: You may submit comments, identified by Docket Number EH-RM-
02-835 and/or RIN 1901-AA-95, by any of the following methods:
Federal eRulemaking Portal: http://www.regulations.gov.
Follow the instructions for submitting comments.
E-mail: Peter.O'Connell@eh.doe.gov. Include Docket Number
EH-RM-02-835 and/or RIN 1901-AA-95 in the subject line of the message.
Mail: Mr. Peter O'Connell, Office of Worker Protection
Policy and Programs (EH-52), U.S. Department of Energy, 1000
Independence Avenue, SW., Washington, DC 20585.
Copies of the public hearing transcript, written comments, and any
other docket material may be reviewed and copied between 9 a.m. and 4
p.m., Monday through Friday, except Federal holidays, at the U.S.
Department of Energy Freedom of Information Reading Room, Room 1E-190,
1000 Independence Avenue, SW., Washington, DC 20585, (202) 586-3142.
The docket material for this rulemaking will be filed under ``EH-RM-02-
835.''
The public hearing for this rulemaking will be held at the
following address: DOE Auditorium, 19901 Germantown Road, Germantown,
Maryland 20874-1290.
We encourage all interested persons to email a copy of their
written comments, if possible, to avoid delays that have occurred in
processing mail addressed to the Department. However, we request that
you send one signed copy of your comments for the record.
Copies of any docket material may be reviewed and copied between 9
a.m. and 4 p.m., Monday through Friday, except Federal holidays, at the
U.S. Department of Energy Freedom of Information Reading Room, Room 1E-
190, 1000 Independence Avenue, SW., Washington, DC 20585, (202) 586-
3142. The docket material for this rulemaking will be filed under ``EH-
RM-02-835.''
FOR FURTHER INFORMATION CONTACT: For further information concerning
public participation in this rulemaking proceeding, see Section VI of
this notice of proposed rulemaking (Opportunity for Public Comment).
SUPPLEMENTARY INFORMATION:
I. Introduction and Background for Proposed Changes to 10 CFR Part 820
A. What is the Purpose and History of 10 CFR Part 820?
B. Why is DOE Proposing Changes to 10 CFR Part 820?
C. In General, What are the Proposed Changes to 10 CFR Part 820?
II. Summary of Changes to 10 CFR Part 820
A. What are the Proposed Changes with Respect to References to
the Deputy Assistant Secretary for Naval Reactors?
B. What are the Proposed Changes in the Definition of
``Secretarial Officer'?
C. What are the Proposed Changes Relating to Investigations?
D. What is the Proposed Change Relating to Direction of NNSA
Contractors?
E. What Changes are Being Proposed to the Appendix on
Enforcement Policy?
III. Introduction and Background for Proposed Changes to 10 CFR Part 835
A. What is the Purpose and History of 10 CFR Part 835?
B. Why is DOE Proposing Changes to 10 CFR Part 835?
C. In General, What are the Proposed Changes to 10 CFR Part 835?
IV. Summary of Changes to 10 CFR Part 835
A. What are the Proposed Changes to the Scope of 10 CFR Part 835?
B. What are the Proposed Changes to the Definitions in 10 CFR Part 835?
C. What is the Proposed Change to Radiological Units in 10 CFR Part 835?
D. What is the Effect of the Proposed Change on Radiation
Protection Programs?
E. What is the Proposed Change in the General Requirements for
Monitoring Individuals and Areas in 10 CFR Part 835?
F. What is the Proposed Change in the Monitoring of Packages
Containing Radioactive Material in 10 CFR Part 835?
G. What is the Proposed Change in the Exception for Labeling
Requirements in 10 CFR Part 835?
H. What are the Proposed Changes in the Individual Monitoring
Records Requirements in 10 CFR Part 835?
I. What are the Proposed Changes to Radiation Safety Training?
J. What are the Proposed Changes in the Design and Control
Requirements in 10 CFR Part 835?
K. What are the Proposed Changes in the General Provisions to
Emergency Exposure Situations in 10 CFR Part 835?
L. What are the Proposed Changes to the DAC Values, Introductory
Paragraph, and Footnotes in Appendix A in 10 CFR Part 835?
M. What are the Proposed Changes to the DAC Values, Introductory
Paragraph, and Footnotes in Appendix C in 10 CFR Part 835?
N. What are the Proposed Changes to the Text and Footnotes in
Appendix D in 10 CFR Part 835?
O. What are the Proposed Changes to the Text and Footnote in
Appendix E in 10 CFR Part 835?
P. For these Proposed Changes in 10 CFR Part 835, Does DOE Plan
to Issue Guidance Documents?
Q. Would a Contractor Need to Submit Any Documents for DOE Approval?
V. Procedural Requirements
A. Review Under the National Environmental Policy Act
B. Review Under Executive Order 12866
C. Review Under Regulatory Flexibility Act
D. Review Under the Paperwork Reduction Act of 1995
E. Review Under Executive Order 13132
F. Review Under the Unfunded Mandates Reform Act of 1995
G. Review Under Executive Order 12988
H. Review Under the Treasury and General Government
Appropriations Act, 1999
[[Page 45997]]
I. Review Under Executive Order 13211
J. Review Under the Treasury and General Government
Appropriations Act, 2001
K. Approval of the Office of the Secretary of Energy
VI. Opportunity for Public Comment
A. Written Comments
B. Public Hearing
I. Introduction and Background for Proposed Changes to 10 CFR Part 820
A. What is the Purpose and History of 10 CFR Part 820?
Part 820 sets forth the procedural rules relating to DOE nuclear
safety requirements. Among other things, 10 CFR part 820 sets forth the
process for granting exemptions from nuclear safety requirements and
the process for issuing civil penalties for violations of nuclear
safety requirements. DOE proposed 10 CFR part 820 on December 9, 1991
(56 FR 64290) and issued a clarification on May 15, 1992 (57 FR 20796).
DOE published 10 CFR part 820 as a final rule on August 17, 1993 (58 FR
43680) and amended it on October 8, 1997 (62 FR 52479) and on March 22,
2000 (65 FR 15218).
B. Why is DOE Proposing Changes to 10 CFR Part 820?
The legislation that established the NNSA contained several
provisions that affect 10 CFR part 820. In particular, non-NNSA
personnel (other than the Secretary and Deputy Secretary) are
prohibited from giving direction to NNSA contractors. In addition,
several Assistant Secretaries and the Deputy Assistant Secretary for
Naval Reactors were converted into NNSA Deputy Administrators. Since
the establishment of the NNSA, 10 CFR part 820 has been applied in a
manner consistent with these provisions. The proposed changes would
revise 10 CFR part 820 to reflect these provisions explicitly.
C. In General, What are the Proposed Changes to 10 CFR Part 820?
The proposed changes to 10 CFR part 820 would: (1) Revise
references to the Deputy Assistant Secretary for Naval Programs to
reflect conversion of the Deputy Assistant Secretary into a Deputy
Administrator; (2) include NNSA Administrator and Deputy Administrators
in the definition of Secretarial Officer; (3) clarify that, with
respect to NNSA contractors, the Secretarial Officer primarily
responsible for environment, safety and health matters is the NNSA
Deputy Administrator with such responsibility; (4) formalize the use of
enforcement letters; and (5) make explicit the role of NNSA in giving
direction to NNSA contractors pursuant to 10 CFR part 820.
II. Summary of Changes to 10 CFR Part 820
A. What are the Proposed Changes with Respect to References to the
Deputy Assistant Secretary for Naval Reactors?
The NNSA Act converted the Deputy Assistant Secretary for Naval
Reactors into the Deputy Administrator for Naval Reactors. DOE is
proposing to revise 820.1(c) by replacing the phrase ``Assistant
Secretary for Naval Reactors'' with ``Deputy Administrator for Naval
Reactors.'' DOE also is proposing to delete the last sentence in the
definition of ``Secretarial Officer'' because the inclusion of ``Deputy
Administrator'' in the first sentence makes the last sentence
unnecessary. In addition, DOE is proposing to update the citation for
the Naval Nuclear Propulsion Program to include Public Law 106-65. No
substantive change in the treatment of the Office of Naval Reactors
under 10 CFR part 820 is being proposed.
B. What are the Proposed Changes in the Definition of ``Secretarial
Officer''?
The NNSA Act converted several Assistant Secretaries into Deputy
Administrators. DOE is proposing to include the phrase ``Deputy
Administrator'', in addition to the phrase ``NNSA Administrator'', in
the definition of ``Secretarial Officer'' to reflect this change. In
addition, DOE is proposing to add a sentence to the definition of
``Secretarial Officer'' to make clear that, with respect to NNSA
activities, the Secretarial Officer primarily responsible for
environment, safety and health matters is the NNSA Administrator or
NNSA Deputy Administrator with such responsibilities.
C. What Are the Proposed Changes Relating to Investigations?
DOE is proposing to add two new subsections to 820.21 to codify
current practices. Proposed 820.21(g) would recognize the use of
enforcement letters to communicate expectations during an investigation
into a possible violation of a nuclear safety requirement. Proposed
820.21(h) would recognize that the Director may sign, issue and serve
subpoenas during an investigation.
D. What Is the Proposed Change Relating to Direction of NNSA Contractors?
The NNSA Act provides at 50 U.S.C. 2410(b) that non-NNSA personnel
(other than the Secretary and Deputy Secretary) are prohibited from
giving direction to NNSA contractors. Since the establishment of the
NNSA, the NNSA and other elements of DOE, including the Office of
Enforcement, have worked together to ensure 10 CFR part 820 operated in
a manner consistent with section 2410(b). DOE is proposing a new
section (820.13) to codify current practices and make clear that NNSA
is responsible for signing, issuing and serving actions that give
direction to NNSA contractors.
E. What Changes Are Being Proposed to the Appendix on Enforcement Policy?
DOE is proposing to update the Appendix on Enforcement Policy to
reflect the proposed changes to 10 CFR part 820.
III. Introduction and Background for Proposed Changes to 10 CFR Part 835
A. What Is the Purpose and History of 10 CFR Part 835?
10 CFR part 835 sets forth the nuclear safety requirements that
provide radiological protection for DOE workers and members of the
public. DOE proposed 10 CFR part 835 on December 9, 1991 (56 FR 64334)
and published it as final on December 14, 1993, (58 FR 65458). DOE
amended 10 CFR part 835 on November 4, 1998, (63 FR 59662).
B. Why Is DOE Proposing Changes to 10 CFR Part 835?
DOE is proposing changes for a number of reasons. In some cases, an
analysis of the operating experience with 10 CFR part 835 indicates
DOE's needs can be met more effectively if there is a change. In other
cases, the Defense Nuclear Facilities Safety Board or members of the
public have suggested changes. In addition, the International
Commission on Radiological Protection (ICRP) has issued newer
recommendations on areas covered by 10 CFR part 835.
C. In General, What Are the Proposed Changes to 10 CFR Part 835?
The proposed changes to 10 CFR part 835 would: (1) Clarify which
requirements in 10 CFR part 835 apply to radioactive material
transportation, (2) exclude from the scope of 10 CFR part 835 material,
equipment and real property approved for release in accordance with DOE
approved authorized limits which have been approved by a Secretarial
Officer in consultation with the Office of the Assistant Secretary for
Environment, Safety and Health, (3) update the dosimetric models and
dose terms to be consistent with newer recommendations from ICRP,
including use of updated tissue and radiation weighting factors and
updated derived air concentration values, (4) establish derived air
concentration values for tritiated
[[Page 45998]]
particulate aerosols and organically bound tritium, (5) lower the upper
limit on the amount of material which need not be labeled, (6) allow
use of thresholds for recording occupational exposures, (7) establish
derived air concentration default values for radionuclides not listed
in the rule, (8) clarifies the role of NNSA to approve planned special
exposures and approve dosimetry monitoring programs that are
substantially equivalent to those accredited by the DOE Laboratory
Accreditation Program (DOELAP), (9) establish strontium-90
contamination limits based on the percentage of strontium-90 in
contamination consisting of mixed fission products, and (10) revise
values in Appendix E to be consistent with newer dosimetric models and
add values for tritiated particulates and organically bound tritium.
IV. Summary of Changes to 10 CFR Part 835
A. What are the Proposed Changes to the Scope of 10 CFR Part 835?
1. Material, Equipment and Real Property Exclusion. DOE proposes to
amend Sec. 835.1 (Scope) by inserting a new paragraph (b)(6) which
would exclude radioactive material on or within material, equipment and
real property that is approved for release when the radiological
conditions of the material, equipment and real property have been
documented to comply, pursuant to DOE Order 5400.5, Radiation
Protection of the Public and the Environment, with the criteria for
release set forth in a DOE authorized limit which has been approved by
a Secretarial Officer in consultation with the Office of the Assistant
Secretary for Environment, Safety and Health. As DOE moves to a more
risk based approach to radiological protection, inconsistencies may
arise between DOE's occupational radiation protection requirements,
which are prescribed for a specified radiological hazard, and DOE's
environmental radiation protection requirements, which may be applied
based on an assessment of risk. Under DOE Order 5400.5, real property
on a DOE site and material and equipment from a DOE site may be
released for unrestricted or restricted use by members of the public in
accordance with a process to determine the risk to an individual from
the residual radioactive material remaining on or within the material,
equipment or property. Such material, equipment or property may
sometimes contain contaminated surfaces which exceed the surface
contamination levels in 10 CFR part 835 appendix D. The appendix D
values trigger application of occupational radiological control for
contaminated areas. Accordingly, under the current requirements, even
though DOE may have determined that this material, equipment or
property poses a minimal risk to individuals, if DOE activities are
still associated with the material, equipment or property, certain
radiological controls in 10 CFR part 835, such as those for access
control, posting and training must be applied to portions of this
material, equipment or property.
To eliminate this potential inconsistency, DOE proposes a new
section 835.1(b)(6) that would exclude from the scope of 10 CFR part
835 radioactive material on or within material, equipment and real
property which has been approved by DOE for release. This exclusion
would only apply when the radiological conditions of the material,
equipment and property, and the method for meeting the conditions, have
been documented to comply with criteria for release specified in a DOE
authorized limit for that material, equipment and property, and the
criteria have been approved by a Secretarial Officer in consultation
with the Office of the Assistant Secretary for Environment, Safety and
Health. DOE recognizes that, depending on the potential exposure, this
level of approval may be higher than that required by DOE Order 5400.5.
However, this level of approval is consistent with other provisions of
10 CFR part 835 for which there are alternative means of compliance,
such as alternatives to the DOELAP, use of planned special exposures,
and exemption from specified provisions of 10 CFR part 835. The
requirement for consultation with the Office of the Assistant Secretary
for Environment, Safety and Health would be satisfied by providing
copies of a Secretarial Officer's approved authorized limits and
supporting documentation to the cognizant office within the Office of
the Assistant Secretary for Environment, Safety and Health (currently
the Office of Air, Water and Radiation Protection Policy and Guidance
(EH-41)) for review and comment. EH-41 will coordinate the review and
comment with EH-52. After comments have been resolved, the consultation
process is complete. The intent for this proposed change is to allow
for the exclusion to apply even for material, equipment or property
which has not yet been released from DOE control.
2. Radioactive Material Transportation. DOE proposes to revise
section 835.1 to clarify which requirements in 10 CFR part 835 apply to
the transportation of radioactive material by or on behalf of the DOE.
Specifically, existing 835.1(b)(4) would be deleted and replaced by a
new 835.1(d) that would state clearly that subparts F (Entry Control
Program) and G (Posting and Labeling) do not apply to radioactive
material transportation conducted by a DOE individual or DOE
contractor, when the radioactive material is under the continuous
observation and control of an individual who is knowledgeable of and
implements required exposure control measures. This proposed change is
not intended to affect the existing situation where the requirements in
the other subparts of 10 CFR part 835 do apply to radioactive material
transportation.
DOE does not intend Part 835 to apply to transportation by the U.S.
Postal Service or a commercial carrier, such as Fedex or UPS, that
transport radioactive material as part of their normal operations. A
company or subsidiary of a corporation that operates a DOE facility
would not be considered a commercial carrier--even if such an
organization transports radioactive material as part of their
contractual agreement with DOE. This position is consistent with NRC
practice. See, for example, 10 CFR 30.13, 40.12, and 70.12. DOE is
requesting comments as to whether there should be an explicit exclusion
of these carriers.
DOE also is proposing editorial changes to the definition of
``radioactive material transportation'' in Sec. 835.2(a). These
proposed changes are not intended to affect the existing scope of this
definition, which excludes activities related to transportation such as
the preparation of material or packagings for transportation, storage
of material awaiting transportation, or application of markings and
labels required for transportation.
B. What are the Proposed Changes to the Definitions in 10 CFR Part 835?
DOE proposes to change most of the dosimetric terms used in 10 CFR
part 835 to reflect the recommendations for assessing dose and
associated terminology from ICRP Publications 60 and 68. DOE proposes
this change mainly because these recommendations are based on updated
scientific models and more accurately reflect the occupational doses to
workers than the models currently used by DOE, i.e., the models used in
developing Radiation Protection Guidance to Federal agencies for
Occupational Exposures (Environmental Protection Agency, 52 FR 2822,
January 27, 1987) which are based upon 1977 recommendations from the
ICRP. DOE notes that other
[[Page 45999]]
Federal agencies, including the Environmental Protection Agency (EPA),
the Food and Drug Administration, and the National Institute of
Occupational Safety and Health (NIOSH), have already adopted the
current ICRP recommendations in recent guidance documents and
requirements. NIOSH uses the newer recommendations in performing DOE
worker dose assessments under the Energy Employees Occupational Illness
Compensation Program Act of 2000, which is contained in the Floyd D.
Spence National Defense Authorization Act for Fiscal Year 2001 (Public
Law 106-398). The EPA has adopted the recommendations in Federal
Guidance Report Number 13, Cancer Risk Coefficients for Environmental
Exposure to Radionuclides. In addition, recommendations published by
the National Council on Radiation Protection and Measurements (NCRP)
for the past several years, as well as several standards issued by the
American National Standards Institute, have used the newer dosimetric
quantities and units endorsed by the ICRP.
Consistent with the current rule, internal doses would still be
calculated based on a 50 year committed dose. The following ``cross-
walk'' is provided to show the new terms DOE proposes in this
rulemaking and the current definitions of terms that would be replaced:
------------------------------------------------------------------------
Proposed dosimetric
Current dosimetric definitions definitions
------------------------------------------------------------------------
Committed effective dose equivalent....... Committed effective dose.
Committed dose equivalent................. Committed equivalent dose.
Cumulative total effective dose equivalent Cumulative total effective
dose.
Deep dose equivalent...................... Deep equivalent dose.
Dose equivalent........................... Equivalent dose.
Effective dose equivalent................. Effective dose.
Lens of the eye dose equivalent........... Lens of the eye equivalent
dose.
Quality factor............................ Radiation weighting factor.
Shallow dose equivalent................... Shallow equivalent dose.
Weighting factor.......................... Tissue weighting factor.
Total effective dose equivalent........... Total effective dose.
------------------------------------------------------------------------
Note: Throughout the text of the proposed rule, the above terms would be
revised.
In addition, the following definitions would be revised: Annual
limit on intake, Derived air concentration, Radiation area,
Radiological worker, Dose, External dose or exposure, and Internal dose
or exposure. Also, consistent with ICRP Publication 60, the table of
weighting factors for neutrons would no longer list a column for
neutron flux density.
DOE recognizes that the proposed changes to most of the dosimetric
terms used in 10 CFR part 835 to reflect the recommendations for
assessing dose and associated terminology from ICRP Publications 60 and
68 will require revising many site documents and the updating of
training materials. Although, in June 2004, the ICRP released a draft
of updated recommendations, which include some adjustment of Tissue
Weighting Factors and Radiation Weighting Factors, DOE believes that
this is still an opportune time to make these changes rather than
waiting for the draft recommendations to be finalized. It may be
several years before the ICRP will finalize and issue the revised
recommendations and accompanying dose conversion factors. DOE evaluated
the effect of the proposed revisions to Tissue Weighting Factors on
derivation of dose conversion factors. The evaluation found, for
radionuclides of most interest to DOE, that the ICRP proposed Tissue
Weighting Factors revisions would have minimal impact on the secondary
limits derived using the Tissue Weighting Factors (i.e., the Derived
Air Concentrations and Sealed Radioactive Source Accountability
values). Any future need by DOE to revise weighting factors should have
minimal administrative impact for such activities as revising
procedures and training materials. It is envisioned that, over time,
updated recommendations to make revisions to dosimetry calculation
models will periodically be made by national and international
consensus groups. Given that fact, and the significant financial and
resource impact, DOE recognizes that historical doses, recorded and
reported to individuals prior to the effective implementation date of
this proposed amendment, should still be considered to be the official
dose of record. Barring some other unforeseen reason, e.g., discovery
of a site or vendor specific miscalculation in assigned doses, DOE
would not require the updating of historical doses to reflect these
changes. DOE considered several options for this proposed change including:
Allowing sites to choose either converting to the newer
dosimetric terminology and Tissue and Radiation Weighting Factors or
remaining with the existing terminology and Tissue and Radiation
Weighting Factors;
Not specifying in the Rule a specific set of Tissue and
Radiation Weighting Factors, but requiring sites to specify in their
DOE approved Radiation Protection Program the weighting factors to be
used and the technical basis for that determination;
Updating the Tissue and Radiation Weighting Factors to
reflect the newer research without revising the dose terminology;
Updating the Tissue and Radiation Weighting Factors to
reflect the newer research and revising the dose terminology; and
Converting to the newer dosimetric terminology and Tissue
and Radiation Weighting Factors and not updating the Derived Air
Concentration values (Appendices A and B to part 835) and Appendix E to
part 835 values.
DOE considers the best approach to convert all terminology and
methodology, including the appendix A, B and E to part 835 values, to
reflect ICRP Publications 60 and 68. However, DOE solicits comments on
these different options.
DOE recognizes that the dosimetric changes will result in the need
to update numerous site documents and proposes a three year
implementation schedule to alleviate the burden of making the changes
(i.e., many of the changes can be made during the regularly scheduled
document updating processing). An extended implementation date also
would recognize that the benefit of updating documents to reflect the
dosimetric changes may not justify the cost at sites nearing closure.
For closure sites which are scheduled to continue operation beyond the
implementation date for the proposed changes, the exemption process in
10 CFR part 820 may be used to request relief, if appropriate. DOE
requests input on any other constructive ways to reduce the costs of
implementing this proposed change.
As discussed in other sections of this preamble, the definitions of
``authorized limit'' and ``real property'' would be added and the
definition of ``radioactive material transportation'' would be revised.
C. What Is the Proposed Change to Radiological Units in 10 CFR Part 835?
DOE proposes to revise the text of Sec. 835.4 to allow use of
additional units, such as dpm, mass units, uCi/cc, and dpm/
100cm2, in records required by this part. The original
intent of this provision was to preclude the exclusive use of the SI
units of becquerel, gray and sievert. The intent was not to preclude
use of other conventional units, such as the ones previously listed. This
[[Page 46000]]
proposed change would achieve the original intent.
D. What Is the Effect of the Proposed Change on Radiation Protection
Programs?
DOE is proposing to add a new sentence at the end of Sec.
835.101(f) that would read ``Unless otherwise specified in this part,
compliance with the amendment to this part published on August 10,
2006, [DATE OF PUBLICATION IN THE FR] shall be achieved no later than
[DATE 3 YEARS FOLLOWING THE EFFECTIVE DATE OF THE FINAL RULE].'' DOE is
proposing to require compliance with the amended requirements of this
part to be achieved no later than three years after the effective date
of this amendment. The reasons for an extended implementation date are
the same as those discussed in connection with the proposed changes to
the dosimetric terms.
E. What Is the Proposed Change in the General Requirements for
Monitoring Individuals and Areas in 10 CFR Part 835?
DOE proposes to amend Sec. 835.401(a)(5) by revising the text
``engineering and process controls'' to read ``engineering and
administrative controls''. This change is proposed in order to make the
use of the terms consistent with DOE Policy 450.4 ``Safety Management
System Policy''. DOE considers the terms to be equivalent.
F. What Is the Proposed Change in the Monitoring of Packages Containing
Radioactive Material in 10 CFR Part 835?
Certain DOE sites have stated that the requirement in Sec.
835.405(c)(2) to perform a measurement of radiation levels was unclear.
Under this provision, a measurement of radiation levels is required for
receipt of packages of radioactive material ``unless the package
contains less than a Type A quantity (as defined at 10 CFR 71.4) of
radioactive material''. The definition of a Type A quantity in 10 CFR
71.4 is a quantity of radioactive material which does not exceed a
value provided in a specified table. Any quantity of radioactive
material less than or equal to the value provided in the table is a
Type A quantity. For example, if the table lists a quantity of 16
Curies (Ci) for an isotope, any quantity of that isotope up to and
including 16 Ci is a Type A quantity. DOE received statements that the
only quantity less than a Type A quantity would be a zero quantity or a
negative quantity.
The intent of the requirement has always been that a measurement of
the radiation level is required for receipt of packages containing more
than a Type A quantity. Title 10 CFR 71.4 defines a Type B quantity as
a quantity of radioactive material which exceeds a Type A quantity.
Accordingly, to clarify the requirement, DOE proposes to amend Sec.
835.405(c)(2) by changing ``unless the package contains less than a
Type A quantity'' to ``if the package contains a Type B quantity''.
G. What Is the Proposed Change in the Exception for Labeling
Requirements in 10 CFR Part 835?
DOE proposes to establish an upper limit of 0.1 Ci for a quantity
of radioactive material which would be excepted from the labeling
requirement in Sec. 835.606(a)(2). After the establishment of the
radioactive material labeling requirements in the 1998 amendment to 10
CFR part 835, it was noted that the exception to labeling requirements
for radioactive materials appeared excessive for certain isotopes. DOE
exempts from labeling items and containers if a quantity of radioactive
material is less than one tenth of the values specified in appendix E
of 10 CFR part 835. For some isotopes this quantity is significant. For
example, a container of tritiated water does not need to be labeled
``Caution, Radioactive Material'' as long as there is less than 16 Ci
of tritiated water in the container. While the basis for this
exception, as discussed in the preamble to the 1998 amendment to 10 CFR
part 835, is technically defensible, DOE believes that it is prudent to
establish an upper limit for the labeling exception. The approach DOE
is proposing is similar to that taken by the NRC, with the exception
that the NRC upper limit is 0.001 Ci. DOE believes that the 0.1 Ci
upper limit would provide an acceptable level of protection, based on
the exposure scenario discussed in the preamble to the 1998 amendment
(63 FR 59662), and still provides for sufficient operational flexibility
in not being overly restrictive in the labeling requirements.
H. What Are the Proposed Changes in the Individual Monitoring Records
Requirements in 10 CFR Part 835?
DOE proposes to revise Sec. 835.702(b) to give sites the option of
not assessing and recording any internal dose monitoring result
estimated to be less than 10 millirem committed equivalent dose. This
change is proposed in response to concerns that, under the current
requirements, there is no threshold of positive internal dose
monitoring result which need not be assessed and a dose recorded. DOE
believes that this flexibility will be of most benefit for routine
bioassay results from tritium and uranium operations. In particular for
tritium, current requirements for recording internal doses may be
considered to be overly burdensome. For tritium, positive bioassay
results could result in needing to determine and record doses that are
less than one millirem. The proposed revision allows some relief from
needing to perform a dose assessment and to record these very small
doses. This may most easily be achieved through the development and use
of default values, below which no further dose assessment or recording
is required. Establishing a dose threshold for any single bioassay and/
or air monitoring result makes the DOE requirements consistent with
nationally accepted standards as discussed in American National
Standard for Design of Internal Dosimetry Programs (ANSI/HPS N13.39-
2000). The provision still requires the maintenance of bioassay and/or
air monitoring results in case they are needed by DOE in the future.
DOE's policy has been that the current monitoring threshold of 100
millirem should not be interpreted as an objective for internal dose
monitoring (i.e., DOE fully recognizes that routine internal dose
monitoring is not capable of detecting doses at the monitoring
threshold for some radionuclides). Consistent with that policy, these
proposed threshold values for assessing internal dose should not be
construed as the establishment of thresholds for internal dose monitoring.
The proposed revision would provide flexibility for assessing and
recording doses for any single bioassay and/or air monitoring result
and also includes an annual limit for doses that need not be assessed
or recorded based on 50 percent of the applicable monitoring threshold
at Sec. Sec. 835.402(c)(1) through (4). DOE recognizes that sites
wishing to invoke the flexibility offered by this proposed change would
need to develop and implement a program to track bioassay results to
ensure that dose constraints are not exceeded without recording the
doses. DOE will provide guidance on acceptable implementation methods.
I. What Are the Proposed Changes to Radiation Safety Training?
DOE proposes to amend Sec. 835.901(b) by adding the text ``applied
training,'' after ``by successful completion of.'' The training and
applied training is to be commensurate with the hazards in the area and
the required controls. DOE already requires, in Sec. 835.901(c), that
[[Page 46001]]
each individual demonstrate knowledge of the radiation safety training
topics by successful completion of an examination and performance
demonstrations. The current requirement for performance demonstration
implies that the training will include practical factors or ``applied
training''. Accordingly, DOE considers the proposed change to be only
editorial.
DOE is considering options for adding a provision for retention
testing. DOE has provided, and still maintains several guidance
documents which address retention testing. These include:
DOE G 441.1-12, Radiation Safety Training Implementation Guide
DOE-STD-1098-99, Radiological Control
DOE-HDBK-1131-98, General Employee Radiological Training
DOE-HDBK-1130-98, Radiological Worker Training
In particular, DOE-HDBK-1131-98 includes an attachment ``Evaluating
the Effectiveness of Radiological Training.'' This attachment discusses
a recommended approach to implementing a retention testing program. DOE
is soliciting comments on including, in 10 CFR part 835, a requirement
for retention testing.
In addition, DOE is soliciting comments on adding a provision, in
subpart J, for radiological control technician (RCT) training.
Currently, 10 CFR part 835 requires individuals responsible for
developing and implementing measures necessary for ensuring compliance
with the requirements of 10 CFR part 835 to have the appropriate
education, training, and skills. This provision applies to RCTs. To
assist sites in meeting this requirement, DOE has provided, and
continues to maintain, several guidance documents discussing the
training, retraining and qualifications of RCTs. These include:
DOE G 441.1-1, Management and Administration of Radiation
Protection Programs Implementation Guide
DOE-STD-1098-99, Radiological Control
DOE STD-1107-97, Knowledge, Skills, and Abilities for Key
Radiation Protection Positions at DOE Facilities
DOE-DBK-1122-99, Radiological Control Technician Training.
All of the above provide guidance on DOE's expectations for the
appropriate level of training, retraining, testing and qualification of
RCTs. DOE is soliciting comments on including, in 10 CFR part 835,
requirements for RCT of training, retraining, testing and qualification.
J. What Are the Proposed Changes in the Design and Control Requirements
in 10 CFR Part 835?
DOE proposes to amend Sec. 835.1001(a) by replacing the text
``physical design features and administrative control'' with
``engineering and administrative controls''. DOE also proposes to amend
Sec. 835.1001(b) by replacing the text ``physical design features''
with ``engineering controls'' and proposes to amend Sec. 835.1003 by
replacing the text ``physical design features and administrative
controls'' with ``engineering and administrative controls''. These
changes are proposed in order to make the use of the terms consistent
with DOE Policy 450.4 ``Safety Management System Policy''. DOE
considers the terms to be equivalent.
K. What Are the Proposed Changes in the General Provisions to Emergency
Exposure Situations in 10 CFR Part 835?
DOE proposes to amend the general provisions to emergency exposure
situations to clarify that the resumption of operations, pursuant to
Sec. 835.1301(d), only applies to operations which have been suspended
as a result of a dose in excess of the limits specified in section
Sec. 835.202. DOE considers the proposed change to be only editorial.
L. What Are the Changes to the DAC Values, Introductory Paragraph, and
Footnotes in Appendix A to 10 CFR Part 835?
One of the options discussed earlier in this preamble is the
adoption of the system of dosimetry for intake of radioactive materials
set forth in more recent ICRP Publications. Because provisions
pertaining to the control of internal dose reference appendix A, DOE
proposes to modify the derived air concentration values contained in
appendix A to reflect the previously mentioned ICRP publications. The
salient changes would be:
The use of updated dose per unit intake conversion factors
specified in ICRP Publication 68 instead of the dose per unit intake
conversion factors in the EPA Federal Guidance Report Number 11,
Limiting Values of Radionuclide Intake and Air Concentration and Dose
Conversion Factors for Inhalation, Submersion, and Ingestion, which is
the basis for the current appendix A values. ICRP Publication 68 lists
committed effective dose coefficients which are used in deriving the
derived air concentration limit based on the stochastic limit of 5 rem.
In order to determine if the non-stochastic (organ) limit of 50 rem to
any organ or tissue is more limiting, DOE used the ICRP computer
program, The ICRP Database of Dose Coefficients: Workers and Members of
the Public, ISBN 0 08 043 8768. As in the current set of derived air
concentration values, the more limiting value (stochastic or non-
stochastic) is used.
The use of the ICRP Publication 66 classification of
radioactive material by absorption rate [F(fast), M(medium), and
S(slow)] instead of by lung clearance classes [D(days), W(weeks), and
Y(years)] as specified in ICRP Publication 30.
The use of default particle size distribution of 5 [mu]m
instead of a default particle size distribution of 1 [mu] if the actual
particle size distribution is not known.
These proposed changes are explained in the introduction to appendix A.
In addition to the changes in the dosimetric models used to
calculate the DACs in appendix A, several other changes to this
appendix are proposed. One proposed change is to establish derived air
concentration values for tritiated particulate aerosols, insoluble
organically bound tritium and default values for radionuclides not
listed in the appendix.
Subsequent to the November 4, 1998, amendment to 10 CFR part 835,
Occupational Radiation Protection (63 FR 59662), the Department and its
contractors have been researching and developing appropriate guidance
for individual exposure to tritiated particulate aerosols and insoluble
organically bound tritium. In 1999, the DOE Office of Worker Protection
Policy and Programs (EH-52) issued Radiological Control Technical
Position RCTP 99-02, Acceptable Approach for Developing Air
Concentration Values for Controlling Exposures to Tritiated Particulate
Aerosols and Organically-Bound Tritium, which provided guidance on use
of acceptable air concentration values. In 2004 EH-52 also published a
technical standard, Radiological Control Programs for Special Tritium
Compounds, DOE-HDBK-1184-2004, which provides additional guidance on
use of acceptable air concentration values. The ICRP publications do
not list dose coefficients for tritiated particulate aerosols and do
not specifically address insoluble organically bound tritium.
Therefore, DOE proposes including derived air concentration values for
these substances based on the methodology described in DOE-HDBK-1184-
2004, adjusted to use the ICRP 60 dosimetric quantities. This handbook
[[Page 46002]]
http://www.eh.doe.gov/radiation/ts.html and the Freedom of Information Reading Room.
Appendix A to 10 CFR part 835 does not include default values for
radionuclides not listed in the appendices. Consistent with the NRC
practice, DOE proposes to establish default values for radionuclides
not listed in appendix A. One default value would apply for any isotope
not already listed with a decay mode other than alpha emission or
spontaneous fission and with a radioactive half-life greater than two
hours. The default value would be the most restrictive applicable
derived air concentration value already listed in appendix A for that
type of decay, i.e., 1.E-10 [mu]Ci/ml (4 Bq/m3). The second
default value would apply for any isotope not already listed with a
decay mode of alpha emission or spontaneous fission, or any mixture for
which the identity or the concentration of any radionuclide in the
mixture is not known. The default value would likewise be the most
restrictive applicable derived air concentration value already listed
in appendix A, i.e., 2.E-13 [mu]Ci/ml (8.E-03 Bq/m3).
M. What Are the Proposed Changes to the DAC Values, Introductory
Paragraph, and Footnotes in Appendix C to 10 CFR Part 835?
DOE proposes to amend appendix C to 10 CFR part 835 by changing the
term ``contaminated atmospheric cloud'' to ``cloud of airborne
radioactive material''. DOE considers this change to be only editorial.
Consistent with DOE's proposal to adopt the system of dosimetry for
intake of radioactive materials set forth in more recent ICRP
publications, DOE proposes to replace the air immersion derived air
concentration values in appendix C with new values which were
determined using ICRP Publication 68 methodology. Specifically, the
proposed values are derived from the dose conversion factors in Annex D
of ICRP publication 68 and assumes 250 days (50 weeks times 5 days per
week) exposure per year to get an effective dose of 5 rem in a year.
Consistent with the NRC, DOE also proposes to establish a default value
for any single radionuclide not listed in the appendix. The default
value would apply for any isotope not already listed with a decay mode
other than alpha emission or spontaneous fission and with a radioactive
half-life less than two hours. The derived air concentration would be
the most restrictive value already listed, i.e., 6.E-06 [mu]Ci/ml
(2.E+04 Bq/m3).
N. What Are the Proposed Changes to the Text and Footnotes in Appendix
D to 10 CFR Part 835?
Several changes to appendix D are proposed in order to codify
guidance issued by the Department in Radiological Control Technical
Positions (RCTP) and to enhance the clarity of this section. In 10 Code
of Federal Regulations Part 835 Appendix D--Surface Radioactivity
Values, RCTP 96-02, DOE provided guidance on the application of
footnote 5 to this appendix that addresses surface contamination values
for mixed fission products containing Sr-90. Based on this guidance,
DOE proposes to revise appendix D as follows: In the second group of
nuclides (total surface radioactivity value--1000 dpm/100
cm2; removable surface radioactivity value--200 dpm/100
cm2) the parenthetical phrase ``including mixed fission
products where the Sr-90 fraction is 90 percent or more of the total
activity'' would be inserted. A new group would be added to appendix D
(between the existing second and third groups) that consists of mixed
fission products where the Sr-90 fraction is more than 50 percent but
less than 90 percent of the total activity. For this new group, the
total surface radioactivity value would be 3000 dpm/100 cm2
and the removable surface radioactivity value would be 600 dpm/100
cm2. In the group of beta-gamma emitters (total surface
radioactivity value--5000 dpm/100 cm2; removable surface
radioactivity value--1000 dpm/100 cm2) the term ``Sr-90 and
others'' would be replaced by the word ``those''.
In addition, DOE proposes to clarify footnote seven to Appendix D
by replacing the term ``(alpha)'' with the sentence ``These limits only
apply to the alpha emitters within the respective decay series.
DOE is not proposing changes to the surface radioactivity values in
Appendix D at this time. DOE is aware of newly developed surface
radioactivity criteria (see American National Standard--Surface and
Volume Radioactivity Standards for Clearance (ANSI/HPS N13.12-1999)),
for the release of property and other items, which are more clearly
based on potential risks than the surface contamination values in
appendix D. However, to maintain a consistent application in the use of
surface radioactivity values for both protection of workers and for
protection of the public and the environment, DOE intends to continue
evaluation of appendix D surface contamination values as a coordinated
project that addresses both occupational and environmental aspects of
this topic.
DOE-HDBK-1184-2004 recommends applying the 10 CFR part 835 subpart
L provisions when the contamination levels from insoluble tritiated
particles fixed to a surface exceed the removable tritium limit. DOE is
soliciting comments on the need to revise the rule to reflect this
recommendation.
O. What Are the Proposed Changes to the Text and Footnote in Appendix E
to 10 CFR Part 835?
As discussed earlier, DOE proposes to adopt the system of dosimetry
for intake of radioactive materials set forth in more recent ICRP
Publications. The appendix E values would be revised using the ICRP 60
methodology and using the same exposure scenarios as were discussed in
the 1998 amendment to 10 CFR part 835. In summary, the values would be
based on the more limiting of the quantity of radioactive material
which results in either an external or internal whole body dose, from
either inhalation or ingestion, of 100 millirem. The external exposure
scenario assumes a photon exposure for 12 hours a day for 365 days with
the source distance being at 1 meter. The internal exposure scenario
assumes an instantaneous intake of 0.001% of the material by an
individual. Consistent with the other proposed changes, appendix E
values have been recalculated to reflect the previously mentioned ICRP
publications.
DOE also proposes to add a footnote to appendix E that any type of
tritiated particulate aerosol or organically-bound tritiated compound
has a value of 10 Ci. This proposed change would be made to keep
appendix E consistent with the proposed change to appendix A which
includes the addition of tritiated compounds. The value of 10 Ci was
derived using the same method as the other proposed values in appendix
E, i.e., they are based on the exposure scenario discussed in the
preamble to the 1998 amendment. Specifically, the inhalation exposure
scenario used to derive the 10 Ci value assumes a 100 mrem dose from a
Type S hafnium tritide particle (the most restrictive tritiated
particulate aerosol or organically-bound tritiated compound) with a
release fraction to be inhaled of 0.001%. A dose conversion value of
2.6 E-10 Sv/Bq, using the methodology from Radiological Control
Programs for Special Tritium Compounds, DOE-HDBK-1184-2004, adjusted to
using the ICRP 60 dosimetric quantities, was used.
In addition, the appendix E value for Californium-252, which decays by
[[Page 46003]]
spontaneous fission emitting neutrons, would be lower if the external
exposure assumption was for neutron instead of photon exposure.
Accordingly, DOE calculated the proposed appendix E value for
Californium-252 by substituting a neutron exposure for the photon
exposure in the external exposure scenario using values from Reference
Neutron Radiations--Part 1: Characteristics and Methods of Production,
ISO/CD, 8529-1.
P. For These Proposed Changes in 10 CFR Part 835, Does DOE Plan To
Issue Guidance Documents?
The primary implementation guides which define DOE's expectations
for the existing rule are the DOE G 441.1 series of 13 Implementation
Guides for use with 10 CFR part 835. All of these guides are available
through the DOE directives Web page on
``http://www.directives.doe.gov/serieslist.html''.
DOE plans on updating these 13 guides to reflect the amended
requirements. DOE also plans to review and, as necessary, incorporate
the DOE Radiological Control Technical Positions issued by the DOE
Office of Worker Protection Policy and Programs into the Implementation
Guides. DOE Technical Standards developed by the DOE Office of Worker
Protection Policy and Programs will be updated as part of their routine
five year reaffirmation process. In particular, these Technical
Standards include: DOE-STD-1098-99 Radiological Control, DOE-STD-1121-
98 Internal Dosimetry and the series of handbook relating to radiation
protection training.
Q. Would a Contractor Need To Submit Any Documents for DOE Approval?
Section 835.101(g) requires contractors to update their Radiation
Protection Program (RPP) and submit it to the DOE within 180 days of
the effective date of any modifications to part 835. In accordance with
10 CFR 835.101(f), the RPP shall include plans, schedules, and other
measures for achieving compliance no later than three years following
the effective date of the amendment. DOE has issued guidance on
submittal of RPPs in DOE G 441.1-1A, Management and Administration of
Radiation Protection Programs.
V. Procedural Requirements
A. Review Under the National Environmental Policy Act
DOE has reviewed these proposed amendments to 10 CFR parts 820 and
835 under the National Environmental Policy Act (NEPA) of 1969 (42
U.S.C. 4321 et seq.), the Council on Environmental Quality's
regulations (40 CFR parts 1500-08), and DOE's implementing regulations
(10 CFR part 1021). Categorical Exclusion A5 in Appendix A to Subpart D
of 10 CFR part 1021 (rulemaking that amends an existing rule without
changing the environmental effect of the amended rule) applies to this
rulemaking. Accordingly, DOE has not prepared an environmental impact
statement or an environmental assessment pursuant to NEPA.
B. Review Under Executive Order 12866
This proposed rule has been determined not to be a ``significant
regulatory action'' within the scope of section 3(f) of the Executive
Order 12866, ``Regulatory Planning and Review'' (58 FR 51735, October
4, 1993. Accordingly, this proposed rule was not reviewed under the
Executive Order by the Office of Information and Regulatory Affairs in
the Office of Management and Budget.
C. Review Under Regulatory Flexibility Act
The Regulatory Flexibility Act, 5 U.S.C. 601 et seq., requires that
a Federal agency prepare a regulatory flexibility analysis for any rule
for which the agency is required to publish a general notice of
proposed rulemaking. The requirement to prepare an analysis does not
apply, however, if the agency certifies that a rule will not have a
significant economic impact on a substantial number of small entities.
As required by Executive Order 13272, ``Proper Consideration of Small
Entities in Agency Rulemaking,'' 67 FR 53461 (August 16, 2002), DOE
published procedures and policies on February 19, 2003, to ensure that
the potential impacts of its rules on small entities are properly
considered during the rulemaking process (68 FR 7990). DOE has made its
procedures and policies available on the Office of General Counsel's
Web site: http://www.gc.doe.gov.
The impact of the changes to 10 CFR part 820 are primarily for
DOE's administration of its enforcement program. The impact of the
changes to 10 CFR part 835 are primarily with respect to large
management and operating contractors. Subcontractors and suppliers are
expected to satisfy the provisions of 10 CFR part 835 primarily through
the programs and procedures established by prime contractors. The
impacts to small entities with respect to changes to 10 CFR parts 820
and 835 are expected to be minor and the costs of compliance are
reimbursable under contracts with DOE. On this basis, DOE certifies
that this rule will not have a significant economic impact on a
substantial number of small entities and, therefore, no analysis has
been prepared.
D. Review Under the Paperwork Reduction Act of 1995
The information collection provisions of this proposed rule are not
substantially different from those contained in DOE contracts with DOE
prime contractors covered by this proposed rule. The information
collection was previously approved by the Office of Management and
Budget (OMB) and assigned OMB Control No. 1910-0300. Accordingly, no
additional Office of Management and Budget clearance is required by the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
E. Review Under Executive Order 13132
Executive Order 13132 (64 FR 43255, August 10, 1999), requires
agencies to develop an accountable process to ensure meaningful and
timely input by State and local officials in the development of
regulatory policies that have ``federalism implications.'' Policies
that have federalism implications are defined in the Executive Order to
include regulations that have substantial direct effects on the States,
on the relationship between the national government and the States, or
on the distribution of power and responsibilities among the various
levels of government. DOE has examined the proposed changes to 10 CFR
parts 820 and 835 and determined that they do not have a substantial
direct effect on the States, on the relationship between the national
government and the States, or on the distribution of power and
responsibilities among various levels of government. No further action
is required by Executive Order 13132.
F. Review Under the Unfunded Mandates Reform Act of 1995
Title II of the Unfunded Mandates Reform Act of 1995, 2 U.S.C. 1531
et seq., requires each Federal agency, to the extent permitted by law,
to prepare a written assessment of the effects of any Federal mandate
in an agency rule that may result in the expenditure by State, local,
and tribal governments, in the aggregate or by the private sector, of
$100 million or more (adjusted annually for inflation) in any one year.
This proposed rule would amend 10 CFR parts 820 and 835. The 10 CFR
part 835 changes would apply only to activities conducted by or for DOE
[[Page 46004]]
involving individual exposure to ionizing radiation. Any costs
resulting from implementation of DOE's management, operation, and
enforcement of its nuclear safety program are ultimately borne by the
Federal Government. Therefore, the requirements of Title II of the
Unfunded Mandates Reform Act of 1995 do not apply.
G. Review Under Executive Order 12988
With respect to the review of existing regulations and the
promulgation of new regulations, section 3 of Executive Order 12988,
``Civil Justice Reform,'' 61 FR 4729 (February 7, 1996), imposes on
Executive agencies the general duty to eliminate drafting errors and
ambiguity, write regulations to minimize litigation, provide a clear
legal standard for affected conduct rather than a general standard, and
promote simplification and burden reduction. Section 3(c) of Executive
Order 12988 requires Executive agencies to review regulations in light
of applicable standards in section 3(a) and section 3(b) to determine
whether they are met. DOE has completed the required review and
determined that, to the extent permitted by law, this notice of
proposed rulemaking to amend 10 CFR parts 820 and 835 meets the
relevant standards of Executive Order 12988.
H. Review Under the Treasury and General Government Appropriations Act,
1999
Section 654 of the Treasury and General Government Appropriations
Act, 1999 (Pub. L. 105-277) requires Federal agencies to issue a Family
Policymaking Assessment for any proposed rule or policy that may affect
family well-being. The proposed amendments to 10 CFR parts 820 and 835
would not impact on the autonomy or integrity of the family
institution. Accordingly, DOE has concluded that it is not necessary to
prepare a Family Policymaking Statement.
I. Review under Executive Order 13211
Executive Order 13211, ``Actions Concerning Regulations That
Significantly Affect Energy Supply, Distribution, or Use'' (66 FR
28355, May 22, 2001) requires Federal agencies to prepare and submit to
the Office of Information and Regulatory Affairs in the Office of
Management and Budget a Statement of Energy Effects for any significant
energy action. Today's proposed rule is not a significant energy
action, as that term is defined in the Executive Order. Accordingly,
DOE has not prepared a Statement of Energy Effects.
J. Review Under the Treasury and General Government Appropriations Act,
2001
The Treasury and General Government Appropriation Act, 2001 (44
U.S. C. 3516, note) provides for agencies to review most dissemination
of information to the public under guidelines established by each
agency pursuant to general guidelines issued by OMB. OMB'S guidelines
were published at 67 FR 8452 (February 22, 2002), and DOE's guidelines
were published at 67 FR 62446 (October 7, 2002). DOE has reviewed
today's notice under the OMB and DOE guidelines and has concluded that
it is consistent with applicable policies in those guidelines.
K. Approval of the Office of the Secretary of Energy
The Office of the Secretary has approved the issuance of this
notice of proposed rulemaking.
VI. Opportunity for Public Comment
A. Written Comments
Interested persons are invited to participate in this proceeding by
submitting data, views, or comments on this proposed rule. Three copies
of written comments should be submitted to the address indicated in the
ADDRESSES section of this notice of proposed rulemaking. Comments
should be identified on the outside of the envelope and on the comments
themselves with the designated ``Docket No. EH-RM-02-835'' or ``RIN
1901-AA95.'' All comments received on or before the date specified at
the beginning of this notice will be considered before final action is
taken in this rulemaking. Because of recent delays in the delivery of
mail to DOE, we recommend that comments also be sent by email to the
address given at the beginning of this notice of proposed rulemaking.
All submitted comments will be available for public inspection as
part of the administrative record for this rulemaking in the DOE
Freedom of Information Reading Room at the address given in the
ADDRESSES section of this notice of proposed rulemaking.
Pursuant to the provisions of 10 CFR 1004.11, anyone submitting
information or data that he or she believes to be confidential and
exempt by law from public disclosure should submit one complete copy of
the document, as well as two copies, if possible, from which the
information has been deleted. DOE will make its determination as to the
confidentiality of the information and treat it accordingly.
B. Public Hearing
A public hearing will be held at the time, date, and location
indicated in the DATES and ADDRESSES sections of this notice. DOE
invites any person who has an interest in the proposed rule, or who is
a representative of a group or class of persons that has an interest,
to make a request for an opportunity to make an oral presentation at
the hearing. Requests to speak should be sent to the mailing address or
e-mail address or made by calling the telephone number given in the
DATES section of this notice. Requests must be received by the time
specified in the DATES section of this notice. The person making the
request should provide a daytime telephone number. Each person selected
to speak at a public hearing will be notified as to his or her
approximate speaking time. DOE reserves the right to select persons to
be heard at each hearing, to schedule their presentations, and to
establish procedures governing the conduct of the hearing. The length
of each presentation will be limited to 10 minutes, unless the hearing
officer determines that the number of persons requesting to speak
permits longer presentation times.
A departmental official will be designated to preside at the
hearing. The hearing will not be a judicial or a trial-type hearing but
will be conducted in accordance with 5 U.S.C. 553 and section 501 of
the Department of Energy Organization Act, 42 U.S.C. 7191. Only those
persons conducting the hearing may ask questions. At the conclusion of
all initial oral statements, each person will be given the opportunity
to make a rebuttal statement. The rebuttal statements will be given in
the same order as the initial statements. Any further procedural rules
needed for the proper conduct of the hearing will be announced by the
Presiding Officer at the hearing.
DOE will retain the record of the full hearing, including the
transcript, and make it available for inspection and copying in the DOE
Freedom of Information Reading Room at the address provided in the
ADDRESSES section of this notice. Transcripts may be purchased from the
court reporter.
If DOE must cancel the hearing, every effort will be made to
publish an advance notice of such cancellation in the Federal Register.
Notice of cancellation also will be given to all persons scheduled to
speak at the hearing. The hearing date may be canceled in the event no
public testimony has been scheduled in advance.
[[Page 46005]]
List of Subjects
10 CFR Part 820
Administrative practice and procedure, Federal buildings and
facilities, Government contracts, Nuclear energy, Nuclear materials,
Nuclear power plants and reactors, Nuclear safety, Penalties, Public
health, and Radiation protection.
10 CFR Part 835
Federal buildings and facilities, Nuclear energy, Nuclear
materials, Nuclear power plants and reactors, Nuclear safety,
Occupational safety and health, Radiation protection, and Reporting and
recordkeeping requirements.
Issued in Washington, DC on July 6, 2006.
C. Russell H. Shearer,
Acting Assistant Secretary for Environment, Safety and Health.
For the reasons set forth in the preamble, Parts 820 and 835 of
Chapter III, Title 10, of the Code of Federal Regulations are proposed
to be amended as set forth below.
PART 820--PROCEDURAL RULES FOR DOE NUCLEAR ACTIVITIES
1. The authority citation for part 820 is revised to read as follows:
Authority: 42 U.S.C. 2201; 2282(a); 7191; 28 U.S.C. 2461 note;
50 U.S.C. 2410.
2. In Sec. 820.1 paragraph (c) is revised to read as follows:
Sec. 820.1 Purpose and Scope.
* * * * *
(c) Exclusion. Activities and facilities covered under E.O. 12344,
42 U.S.C. 7158 note, pertaining to Naval nuclear propulsion are
excluded from the requirements of subparts D and E of this part
regarding interpretations and exemptions related to this part. The
Deputy Administrator for Naval Reactors or his designee will be
responsible for formulating, issuing, and maintaining appropriate records
of interpretations and exemptions for these facilities and activities.
3. In Sec. 820.2 revise the definitions for ``Director'', and
``Secretarial Officer'', and add a new definition for ``NNSA'', in
alphabetical order to read as follows:
Sec. 820.2 Definitions.
* * * * *
Director means a DOE Official to whom the Secretary has assigned
the authority to investigate the nature and extent of compliance with
the requirements of this part. With regard to activities and facilities
covered under E.O. 12344, 42 U.S.C. 7158 note, pertaining to Naval
nuclear propulsion, the Director shall mean the Deputy Administrator
for Naval Reactors or his designee.
* * * * *
NNSA means the National Nuclear Security Administration.
* * * * *
Secretarial Officer means the Assistant Secretary, NNSA
Administrator, Deputy Administrator, Program Office Director, or
equivalent DOE official who has primary line management responsibility
for a contractor.
* * * * *
4. Section 820.13 is added to read as follows:
Sec. 820.13 Direction to NNSA contractors.
(a) Notwithstanding any other provision of this part, and pursuant
to section 3220 of Public Law 106-65, as amended, the NNSA
Administrator, rather than the Director, signs, issues and serves the
following actions that direct NNSA contractors:
(1) Subpoenas;
(2) Orders to compel attendance;
(3) Disclosures of information or documents obtained during an
investigation or inspection;
(4) Preliminary notices of violations; and
(5) Final notices of violations.
(b) The NNSA Administrator shall act after consideration of the
Director's recommendation.
5. In Sec. 820.21, paragraphs (g) and (h) are added to read as follows:
Sec. 820.21 Investigations.
* * * * *
(g) The Director may issue enforcement letters that communicate
DOE's expectations with respect to any aspect of the requirements of
DOE's Nuclear Safety Requirements, including identification and
reporting of issues, corrective actions, and implementation of the
DOE's Nuclear Safety Requirements, provided that an enforcement letter
may not create the basis for any legally enforceable requirement
pursuant to this part.
(h) The Director may sign, issue and serve subpoenas.
6. In Appendix A to part 820, revise sections IV and VIII to read
as follows:
Appendix A to Part 820--General Statement of Enforcement Policy
* * * * *
IV. Responsibilities
(a) The Director, as the principal enforcement officer of the
DOE, has been delegated the authority to:
(1) Conduct enforcement inspections, investigations, and conferences;
(2) Issue Notices of Violations and proposed civil penalties,
Enforcement Letters, Consent Orders, and subpoenas; and
(3) Issue orders to compel attendance and disclosure of
information or documents obtained during an investigation or inspection.
(b) The NNSA Administrator, pursuant to section 3212 of Public
Law 106-65, as amended, has responsibility for environment, safety
and health operations within NNSA and is authorized to sign, issue
and serve the following actions that direct NNSA contractors:
(1) Subpoenas;
(2) Orders to compel attendance;
(3) Disclosure of information or documents obtained during an
investigation or inspection;
(4) Preliminary Notices of Violations; and
(5) Final Notices of Violations.
The NNSA Administrator acts after consideration of the
Director's recommendation.
* * * * *
VIII. Enforcement Letter
(a) In cases where DOE has decided not to conduct an
investigation or inspection or issue a Preliminary Notice of
Violation (PNOV), DOE may send an Enforcement Letter to the
contractor, signed by the Director. Enforcement Letters issued to
NNSA contractors will be coordinated with the Deputy Administrator
of the NNSA with primary responsibility for environment, safety and
health matters prior to issuance. The Enforcement Letter is intended
to communicate the basis of the decision not to pursue enforcement
action for a noncompliance. The Enforcement Letter is intended to
inform contractors of the desired level of worker safety and health
performance. It may be used when DOE concludes the specific
noncompliance at issue is not of the level of significance warranted
to conduct an investigation or inspection or for issuance of a PNOV.
Even where a noncompliance may be significant, the Enforcement
Letter recognizes that the contractor's actions may have attenuated
the need for enforcement action. The Enforcement Letter will
typically recognize how the contractor handled the circumstances
surrounding the noncompliance, address additional areas requiring
the contractor's attention, and address DOE's expectations for
corrective action.
(b) In general, Enforcement Letters communicate DOE's
expectations with respect to any aspect of the requirements of this
part, including identification and reporting of issues, corrective
actions, and implementation of the contractor's safety and health
program. DOE might, for example, wish to recognize some action of
the contractor that is of particular benefit to worker safety and
health that is a candidate for emulation by other contractors. On
the other hand, DOE may wish to bring a program shortcoming to the
attention of the contractor that, but for the lack of worker safety
and health significance of the immediate issue, might have resulted
in the issuance of a PNOV. An Enforcement Letter is not an
enforcement action.
[[Page 46006]]
(c) With respect to many noncompliances, DOE may decide not to
send an Enforcement Letter. When DOE decides that a contractor has
appropriately corrected a noncompliance or that the significance of
the noncompliance is sufficiently low, it may close out its review
simply through an annotation in the DOE Noncompliance Tracking
System (NTS). A closeout of a noncompliance with or without an
Enforcement Letter may only take place after DOE has confirmed that
corrective actions have been completed. Closeout of any NNSA
contractor noncompliance will be coordinated with NNSA prior to closeout.
* * * * *
PART 835--OCCUPATIONAL RADIATION PROTECTION
7. The authority citation for part 835 is revised to read as follows:
Authority: 42 U.S.C. 2201; 7191; 50 U.S.C. 2410.
8. Section 835.1 is amended:
a. In the introductory text of paragraph (b), remove the word
``discussed'' and add in its place ``provided''.
b. Paragraph (b)(2) is revised.
c. Paragraph (b)(4) is removed.
d. Paragraph (b)(5) is redesignated as (b)(4) and the word ``or''
at the end of the paragraph is removed.
e. Paragraph (b)(6) is redesignated as (b)(5) and the period at the
end of the paragraph is removed and ``; or'' is added in its place.
f. A new paragraph (b)(6) is added.
g. Paragraph (c) is revised.
h. A new paragraph (d) is added.
The revisions and additions specified above read as follows:
Sec. 835.1 Scope.
* * * * *
(b) * * *
(2) Activities conducted under the authority of the Deputy
Administrator for Naval Reactors, as described in Public Law 98-525 and
106-65;
* * * * *
(6) Radioactive material on or within material, equipment and real
property which is approved for release when the radiological conditions
of the material, equipment and real property have been documented to
comply with the criteria for release set forth in a DOE authorized
limit which has been approved by a Secretarial Officer in consultation
with the Office of the Assistant Secretary for Environment, Safety and
Health.
(c) Occupational doses received as a result of excluded activities
listed in paragraphs (b)(1) through (b)(4) and (b)(6) of this section,
shall be included to the extent practicable when determining compliance
with the occupational dose limits at Sec. Sec. 835.202 and 835.207,
and with the limits for the embryo/fetus at Sec. 835.206. Occupational
doses resulting from authorized emergency exposures and planned special
exposures shall not be considered when determining compliance with the
dose limits at Sec. Sec. 835.202 and 835.207.
(d) The requirements in subparts F and G of this part do not apply
to radioactive material transportation, provided the radioactive
material is under the continuous observation and control of an
individual who is knowledgeable of and implements required exposure
control measures.
9. Section 835.2 is revised to read as follows:
Sec. 835.2 Definitions.
(a) As used in this part:
Accountable sealed radioactive source means a sealed radioactive
source having a half-life equal to or greater than 30 days and an
isotopic activity equal to or greater than the corresponding value
provided in appendix E of this part.
Airborne radioactive material or airborne radioactivity means
radioactive material dispersed in the air in the form of dusts, fumes,
particulates, mists, vapors, or gases.
Airborne radioactivity area means any area, accessible to
individuals, where:
(1) The concentration of airborne radioactivity, above natural
background, exceeds or is likely to exceed the derived air concentration
(DAC) values listed in appendix A or appendix C of this part; or
(2) An individual present in the area without respiratory
protection could receive an intake exceeding 12 DAC-hours in a week.
ALARA means ``As Low As is Reasonably Achievable,'' which is the
approach to radiation protection to manage and control exposures (both
individual and collective) to the work force and to the general public
to as low as is reasonable, taking into account social, technical,
economic, practical, and public policy considerations. As used in this
part, ALARA is not a dose limit but a process which has the objective
of attaining doses as far below the applicable limits of this part as
is reasonably achievable.
Annual limit on intake (ALI) means the derived limit for the amount
of radioactive material taken into the body of an adult worker by
inhalation or ingestion in a year. ALI is the smaller value of intake
of a given radionuclide in a year by the reference man (ICRP
Publication 23) that would result in a committed effective dose of 5
rems (0.05 sievert) or a committed equivalent dose of 50 rems (0.5
sievert) to any individual organ or tissue. ALI values for intake by
ingestion and inhalation of selected radionuclides are based on
International Commission on Radiological Protection Publication 68,
Dose Coefficients for Intakes of Radionuclides by Workers, published
July, 1994 (ISBN 0 08 042651 4). This document is available from
Elsevier Science Inc., Tarrytown, NY.
Authorized limit means a limit on the concentration of residual
radioactive material on the surfaces or within the property that has
been derived consistent with DOE directives including the as low as is
reasonably achievable (ALARA) process requirements, given the
anticipated use of the property and has been authorized by DOE to
permit the release of the property from DOE radiological control.
Background means radiation from:
(1) Naturally occurring radioactive materials which have not been
technologically enhanced;
(2) Cosmic sources;
(3) Global fallout as it exists in the environment (such as from
the testing of nuclear explosive devices);
(4) Radon and its progeny in concentrations or levels existing in
buildings or the environment which have not been elevated as a result
of current or prior activities; and
(5) Consumer products containing nominal amounts of radioactive
material or producing nominal amounts of radiation.
Bioassay means the determination of kinds, quantities, or
concentrations, and, in some cases, locations of radioactive material
in the human body, whether by direct measurement or by analysis and
evaluation of radioactive materials excreted or removed from the human body.
Calibration means to adjust and/or determine either:
(1) The response or reading of an instrument relative to a standard
(e.g., primary, secondary, or tertiary) or to a series of
conventionally true values; or
(2) The strength of a radiation source relative to a standard
(e.g., primary, secondary, or tertiary) or conventionally true value.
Contamination area means any area, accessible to individuals, where
removable surface contamination levels exceed or are likely to exceed
the removable surface contamination values specified in appendix D of
this part, but do not exceed 100 times those values.
Controlled area means any area to which access is managed by or for
DOE to protect individuals from exposure to radiation and/or
radioactive material.
Declared pregnant worker means a woman who has voluntarily declared
to her employer, in writing, her pregnancy
[[Page 46007]]
for the purpose of being subject to the occupational dose limits to the
embryo/fetus as provided in Sec. 835.206. This declaration may be
revoked, in writing, at any time by the declared pregnant worker.
Derived air concentration (DAC) means, for the radionuclides listed
in appendix A of this part, the airborne concentration that equals the
ALI divided by the volume of air breathed by an average worker for a
working year of 2000 hours (assuming a breathing volume of 2400 m\3\).
For the radionuclides listed in appendix C of this part, the air
immersion DACs were calculated for a continuous, non-shielded exposure
via immersion in a semi-infinite cloud of radioactive material. The
values are based upon International Commission on Radiological
Protection Publication 68, Dose Coefficients for Intakes of
Radionuclides by Workers, published July, 1994 (ISBN 0 08 042651 4).
This document is available from Elsevier Science Inc., Tarrytown, NY.
Derived air concentration-hour (DAC-hour) means the product of the
concentration of radioactive material in air (expressed as a fraction
or multiple of the DAC for each radionuclide) and the time of exposure
to that radionuclide, in hours.
DOE activity means an activity taken for or by DOE in a DOE
operation or facility that has the potential to result in the
occupational exposure of an individual to radiation or radioactive
material. The activity may be, but is not limited to, design,
construction, operation, or decommissioning. To the extent appropriate,
the activity may involve a single DOE facility or operation or a
combination of facilities and operations, possibly including an entire
site or multiple DOE sites.
Entrance or access point means any location through which an
individual could gain access to areas controlled for the purpose of
radiation protection. This includes entry or exit portals of sufficient
size to permit human entry, irrespective of their intended use.
General employee means an individual who is either a DOE or DOE
contractor employee; an employee of a subcontractor to a DOE
contractor; or an individual who performs work for or in conjunction
with DOE or utilizes DOE facilities.
High contamination area means any area, accessible to individuals,
where removable surface contamination levels exceed or are likely to
exceed 100 times the removable surface contamination values specified
in appendix D of this part.
High radiation area means any area, accessible to individuals, in
which radiation levels could result in an individual receiving a deep
equivalent dose in excess of 0.1 rem (0.001 sievert) in 1 hour at 30
centimeters from the radiation source or from any surface that the
radiation penetrates.
Individual means any human being.
Member of the public means an individual who is not a general
employee. An individual is not a ``member of the public'' during any
period in which the individual receives an occupational dose.
Minor means an individual less than 18 years of age.
Monitoring means the measurement of radiation levels, airborne
radioactivity concentrations, radioactive contamination levels,
quantities of radioactive material, or individual doses and the use of
the results of these measurements to evaluate radiological hazards or
potential and actual doses resulting from exposures to ionizing radiation.
Nonstochastic effects means effects due to radiation exposure for
which the severity varies with the dose and for which a threshold
normally exists (e.g., radiation-induced opacities within the lens of
the eye).
Occupational dose means an individual's ionizing radiation dose
(external and internal) as a result of that individual's work
assignment. Occupational dose does not include doses received as a
medical patient or doses resulting from background radiation or
participation as a subject in medical research programs.
Person means any individual, corporation, partnership, firm,
association, trust, estate, public or private institution, group,
Government agency, any State or political subdivision of, or any
political entity within a State, any foreign government or nation or
other entity, and any legal successor, representative, agent or agency
of the foregoing; provided that person does not include the Department
or the United States Nuclear Regulatory Commission.
Radiation means ionizing radiation: alpha particles, beta
particles, gamma rays, X-rays, neutrons, high-speed electrons, high-
speed protons, and other particles capable of producing ions.
Radiation, as used in this part, does not include non-ionizing
radiation, such as radio- or micro-waves, or visible, infrared, or
ultraviolet light.
Radiation area means any area, accessible to individuals, in which
radiation levels could result in an individual receiving a deep
equivalent dose in excess of 0.005 rem (0.05 millisievert) in 1 hour at
30 centimeters from the source or from any surface that the radiation
penetrates.
Radioactive material area means any area within a controlled area,
accessible to individuals, in which items or containers of radioactive
material exist and the total activity of radioactive material exceeds
the applicable values provided in appendix E of this part.
Radioactive material transportation means the movement of
radioactive material by aircraft, rail, vessel, or highway vehicle.
Radioactive material transportation does not include preparation of
material or packagings for transportation, storage of material awaiting
transportation, or application of markings and labels required for
transportation.
Radiological area means any area within a controlled area defined
in this section as a ``radiation area,'' ``high radiation area,''
``very high radiation area,'' ``contamination area,'' ``high
contamination area,'' or ``airborne radioactivity area.''
Radiological worker means a general employee whose job assignment
involves operation of radiation producing devices or working with
radioactive materials, or who is likely to be routinely occupationally
exposed above 0.1 rem (0.001 sievert) per year total effective dose.
Real property means land and anything permanently affixed to the
land such as buildings, fences and those things attached to the
buildings, such as light fixtures, plumbing and heating fixtures, or
other such items that would be personal property if not attached.
Real-time air monitoring means measurement of the concentrations or
quantities of airborne radioactive materials on a continuous basis.
Respiratory protective device means an apparatus, such as a
respirator, worn by an individual for the purpose of reducing the
individual's intake of airborne radioactive materials.
Sealed radioactive source means a radioactive source manufactured,
obtained, or retained for the purpose of utilizing the emitted
radiation. The sealed radioactive source consists of a known or
estimated quantity of radioactive material contained within a sealed
capsule, sealed between layer(s) of non-radioactive material, or firmly
fixed to a non-radioactive surface by electroplating or other means
intended to prevent leakage or escape of the radioactive material.
Sealed radioactive sources do not include reactor fuel elements,
nuclear explosive devices, and radioisotope thermoelectric generators.
[[Page 46008]]
Source leak test means a test to determine if a sealed radioactive
source is leaking radioactive material.
Stochastic effects means malignant and hereditary diseases for
which the probability of an effect occurring, rather than its severity,
is regarded as a function of dose without a threshold, for radiation
protection purposes.
Very high radiation area means any area, accessible to individuals,
in which radiation levels could result in an individual receiving an
absorbed dose in excess of 500 rads (5 grays) in one hour at 1 meter
from a radiation source or from any surface that the radiation penetrates.
Week means a period of seven consecutive days.
Year means the period of time beginning on or near January 1 and
ending on or near December 31 of that same year used to determine
compliance with the provisions of this part. The starting and ending
date of the year used to determine compliance may be changed provided
that the change is made at the beginning of the year and that no day is
omitted or duplicated in consecutive years.
(b) As used in this part to describe various aspects of radiation dose:
Absorbed dose (D) means the average energy absorbed by matter from
ionizing radiation per unit mass of irradiated material. The absorbed
dose is expressed in units of rad (or gray) (1 rad = 0.01 gray).
Committed effective dose (E50) means the sum of the
committed equivalent doses to various tissues or organs in the body
(HT,50), each multiplied by the appropriate weighting factor
(wT)--that is, [sigma]50 =
[Sigma]wTHT,50. Committed effective
dose is expressed in units of rem (or sievert).
Committed equivalent dose (HT,50) means the
equivalent dose calculated to be received by a tissue or organ over a
50-year period after the intake of a radionuclide into the body. It
does not include contributions from radiation sources external to the
body. Committed equivalent dose is expressed in units of rem (or
sievert) (1 rem = 0.01 sievert).
Cumulative total effective dose means the sum of all total
effective dose values recorded for an individual plus, for occupational
exposures received before the implementation date of this amendment,
the sum of all total effective dose equivalent (as defined in the
November 4, 1998 amendment to this rule) values recorded for an
individual, where available, for each year occupational dose was
received, beginning January 1, 1989.
Deep equivalent dose means the equivalent dose derived from
external radiation at a depth of 1 cm in tissue.
Dose is a general term for absorbed dose, equivalent dose,
effective dose, committed equivalent dose, committed effective dose, or
total effective dose as defined in this part.
Effective dose (E) means the summation of the products of the
equivalent dose received by specified tissues or organs of the body
(HT) and the appropriate tissue weighting factor
(wT)--that is, E = [Sigma]wTHT. It
includes the dose from radiation sources internal and/or external to
the body. For purposes of compliance with this part, deep equivalent
dose to the whole body may be used as effective dose for external
exposures. The effective dose is expressed in units of rem (or sievert).
Equivalent dose (HT) means the product of average
absorbed dose (DT,R) in rad (or gray) in a tissue
or organ and a radiation weighting factor (wR). Equivalent
dose is expressed in units of rem (or sievert) (1 rem = 0.01 sievert).
External dose or exposure means that portion of the equivalent dose
received from radiation sources outside the body (i.e., ``external
sources'').
Extremity means hands and arms below the elbow or feet and legs
below the knee.
Internal dose or exposure means that portion of the equivalent dose
received from radioactive material taken into the body (i.e.,
``internal sources'').
Lens of the eye equivalent dose means the external exposure of the
lens of the eye and is taken as the equivalent dose at a tissue depth
of 0.3 cm.
Radiation weighting factor (wR) means the modifying
factor used to calculate the equivalent dose from the average tissue or
organ absorbed dose; the absorbed dose (expressed in rad or gray) is
multiplied by the appropriate radiation weighting factor. The radiation
weighting factors to be used for determining equivalent dose in rem are
as follows:
Radiation Weighting Factors \1\, wR
------------------------------------------------------------------------
Radiation
Type and energy range weighting
factor
------------------------------------------------------------------------
Photons, electrons and muons, all energies \2\.............. 1
Neutrons, energy < 10 keV \3\............................... 5
Neutrons, energy 10 keV to 100 keV \3\...................... 10
Neutrons, energy > 100 keV to 2 MeV \3\..................... 20
Neutrons, energy > 2 MeV to 20 MeV \3\...................... 10
Neutrons, energy > 20 MeV \3\............................... 5
Protons, other than recoil protons, energy > 2 MeV.......... 5
Alpha particles, fission fragments, heavy nuclei............ 20
------------------------------------------------------------------------
\1\ All values relate to the radiation incident on the body or, for
internal sources, emitted from the source.
\2\ Excluding Auger electrons emitted from nuclei bound to DNA.
\3\ When spectral data are insufficient to identify the energy of the
neutrons, a radiation weighting factor of 20 shall be used.
Shallow equivalent dose means the equivalent dose deriving from
external radiation at a depth of 0.007 cm in tissue.
Tissue weighting factor (wT) means the fraction of the
overall health risk, resulting from uniform, whole body irradiation,
attributable to specific tissue (T). The equivalent dose to tissue,
(HT), is multiplied by the appropriate tissue weighting factor to
obtain the effective dose (E) contribution from that tissue. The tissue
weighting factors are as follows:
Tissue Weighting Factors for Various Organs and Tissues
------------------------------------------------------------------------
Tissue
Organs or tissues, T weighting
factor, wT
------------------------------------------------------------------------
Gonads...................................................... 0.20
Red bone marrow............................................. 0.12
Colon....................................................... 0.12
Lungs....................................................... 0.12
Stomach..................................................... 0.12
Bladder..................................................... 0.05
Breast...................................................... 0.05
Liver....................................................... 0.05
Esophagus................................................... 0.05
Thyroid..................................................... 0.05
Skin........................................................ 0.01
Bone surfaces............................................... 0.01
Remainder \1\............................................... 0.05
Whole body \2\.............................................. 1.00
------------------------------------------------------------------------
\1\ ``Remainder'' means the following additional tissues and organs:
adrenal glands, brain, extrathoracic airways, upper large intestine,
small intestine, kidney, muscle, pancreas, spleen, thymus, and uterus.
In those cases in which a single one of the remainder tissues or
organs receives an equivalent dose in excess of the highest dose in
any of the twelve organs or tissues for which a tissue weighting
factor is specified, a tissue weighting factor of 0.025 shall be
applied to that tissue or organ and a tissue weighting factor of 0.025
to the average dose in the rest of the remainder.
\2\ For the case of uniform external irradiation of the whole body, a
tissue weighting factor (wT) equal to 1 may be used in determination
of the effective dose.
Total effective dose (TED) means the sum of the effective dose (for
external exposures) and the committed effective dose (for internal
exposures).
[[Page 46009]]
Whole body means, for the purposes of external exposure, head,
trunk (including male gonads), arms above and including the elbow, or
legs above and including the knee.
(c) Terms defined in the Atomic Energy Act or in 10 CFR part 820
and not defined in this part are used consistent with the meanings
given in the Act or in 10 CFR part 820.
10. Section 835.4 is revised to read as follows:
Sec. 835.4 Radiological units.
Unless otherwise specified, the quantities used in the records
required by this part shall be clearly indicated in special units of
curie, rad, roentgen, or rem, including multiples and subdivisions of
these units, or other conventional units, such as, dpm, dpm/100
cm2 or mass units. The SI units, becquerel (Bq), gray (Gy),
and sievert (Sv), may be provided parenthetically in this part for
reference with scientific standards.
11. Section 835.101 is amended by revising paragraph (f) to read as
follows:
Sec. 835.101 Radiation protection programs.
* * * * *
(f) The RPP shall include plans, schedules, and other measures for
achieving compliance with regulations of this part. Unless otherwise
specified in this part, compliance with the amendments to this part
published on [DATE OF PUBLICATION IN THE FR]
shall be achieved no later
than [DATE 3 YEARS FOLLOWING THE EFFECTIVE DATE OF THE FINAL RULE].
* * * * *
12. Section 835.202 is amended by revising paragraphs (a)(1)
through (a)(4) to read as follows:
Sec. 835.202 Occupational dose limits for general employees.
(a) * * *
(1) A total effective dose of 5 rems (0.05 sievert);
(2) The sum of the deep equivalent dose for external exposures and
the committed equivalent dose to any organ or tissue other than the
skin or the lens of the eye of 50 rems (0.5 sievert);
(3) A lens of the eye equivalent dose of 15 rems (0.15 sievert);
and
(4) The sum of the shallow equivalent dose for external exposures
and the committed equivalent dose to the skin or to any extremity of 50
rems (0.5 sievert).
* * * * *
13. Section 835.203 is revised to read as follows:
Sec. 835.203 Combining internal and external equivalent doses.
(a) The total effective dose during a year shall be determined by
summing the effective dose from external exposures and the committed
effective dose from intakes during the year.
(b) Determinations of the effective dose shall be made using the
tissue weighting factor values provided in Sec. 835.2.
14. In Sec. 835.205 paragraphs (b)(1), (b)(2), (b)(3) introductory
text, and (b)(3)(ii) are revised to read as follows:
Sec. 835.205 Determination of compliance for non-uniform exposure of
the skin.
* * * * *
(b) * * *
(1) Area of skin irradiated is 100 cm \2\ or more. The non-uniform
equivalent dose received during the year shall be averaged over the 100
cm \2\ of the skin receiving the maximum dose, added to any uniform
equivalent dose also received by the skin, and recorded as the shallow
equivalent dose to any extremity or skin for the year.
(2) Area of skin irradiated is 10 cm \2\ or more, but is less than
100 cm \2\. The non-uniform equivalent dose (H) to the irradiated area
received during the year shall be added to any uniform equivalent dose
also received by the skin and recorded as the shallow equivalent dose
to any extremity or skin for the year. H is the equivalent dose
averaged over the 1 cm \2\ of skin receiving the maximum absorbed dose,
D, reduced by the fraction f, which is the irradiated area in cm \2\
divided by 100 cm \2\ (i.e., H = fD). In no case shall a value of f
less than 0.1 be used.
(3) Area of skin irradiated is less than 10 cm \2\. The non-uniform
equivalent dose shall be averaged over the 1 cm \2\ of skin receiving
the maximum dose. This equivalent dose shall:
* * * * *
(ii) Not be added to any other shallow equivalent dose to any
extremity or skin recorded as the equivalent dose for the year.
15. In Sec. 835.206, paragraphs (a) and (c) are revised to read as
follows:
Sec. 835.206 Limits for the embryo/fetus.
(a) The equivalent dose limit for the embryo/fetus from the period
of conception to birth, as a result of occupational exposure of a
declared pregnant worker, is 0.5 rem (0.005 sievert).
* * * * *
(c) If the equivalent dose to the embryo/fetus is determined to
have already exceeded 0.5 rem (0.005 sievert) by the time a worker
declares her pregnancy, the declared pregnant worker shall not be
assigned to tasks where additional occupational exposure is likely
during the remaining gestation period.
16. Section 835.207 is revised to read as follows:
Sec. 835.207 Occupational dose limits for minors.
The equivalent dose limits for minors occupationally exposed to
radiation and/or radioactive materials at a DOE activity are 0.1 rem
(0.001 sievert) total effective dose in a year and 10% of the
occupational dose limits specified at Sec. 835.202(a)(3) and (a)(4).
17. Section 835.208 is revised to read as follows:
Sec. 835.208 Limits for members of the public entering a controlled area.
The total effective dose limit for members of the public exposed to
radiation and/or radioactive material during access to a controlled
area is 0.1 rem (0.001 sievert) in a year.
18. In Sec. 835.401, paragraph (a)(5) is revised to read as follows:
Sec. 835.401 General requirements.
(a) * * *
(5) Verify the effectiveness of engineering and administrative
controls in containing radioactive material and reducing radiation
exposure; and
* * * * *
19. Section 835.402 is amended:
a. Paragraphs (a)(1)(i), (ii), and (iii) are revised.
b. Paragraph (a)(2) is revised.
c. Paragraphs (c)(1) and (c)(2) are revised.
The revisions read as follows:
Sec. 835.402 Individual monitoring.
(a) * * *
(1) * * *
(i) An effective dose of 0.1 rem (0.001 sievert) or more in a year;
(ii) A shallow equivalent dose to the skin or to any extremity of 5
rems (0.05 sievert) or more in a year;
(iii) A lens of the eye equivalent dose of 1.5 rems (0.015 sievert)
or more in a year;
(2) Declared pregnant workers who are likely to receive from
external sources an equivalent dose to the embryo/fetus in excess of 10
percent of the applicable limit at Sec. 835.206(a);
* * * * *
(c) * * *
(1) Radiological workers who, under typical conditions, are likely
to receive a committed effective dose of 0.1 rem (0.001 sievert) or
more from all occupational radionuclide intakes in a year;
(2) Declared pregnant workers likely to receive an intake or
intakes resulting
[[Page 46010]]
in a equivalent dose to the embryo/fetus in excess of 10 percent of the
limit stated at Sec. 835.206(a);
* * * * *
Sec. 835.405 [Amended]
20. Section 835.405 is amended in paragraph (c)(2) by removing
``unless the package contains less than a Type A'' and adding in its
place ``if the package contains a Type B''.
Sec. 835.502 [Amended]
21. Section 835.502 is amended in paragraph (a)(2) and paragraph
(b) introductory text by removing the word ``dose'' before
``equivalent'' and adding it after ``equivalent''.
Sec. 835.602 [Amended]
22. Section 835.602 is amended in paragraph (a) by removing the
word ``equivalent''.
Sec. 835.606 [Amended]
23. Section 835.606 is amended in paragraph (a)(2) by adding ``and
less than 0.1 Ci'' after the word ``part'' and before the punctuation.
24. Section 835.702 is amended:
a. Paragraph (a) is revised.
b. Paragraph (b) is revised.
c. Paragraphs (c)(3)(i), (ii), (iii) and (iv) are revised.
d. Paragraphs (c)(4)(i) and (ii) are revised.
e. Paragraph (c)(5)(i), (ii) and (iii) are revised.
f. Paragraph (c)(6) is revised.
The revisions read as follows:
Sec. 835.702 Individual monitoring records.
(a) Except as authorized by Sec. 835.702(b), records shall be
maintained to document doses received by all individuals for whom
monitoring was conducted and to document doses received during planned
special exposures, unplanned doses exceeding the monitoring thresholds
of Sec. 835.402, and authorized emergency exposures.
(b) Recording of the non-uniform shallow equivalent dose to the
skin is not required if the dose is less than 2 percent of the limit
specified for the skin at Sec. 835.202(a)(4). Any internal dose
estimated to be less than 10 millirem committed equivalent dose need
not be recorded, if the bioassay and/or air monitoring results used to
make the estimate are maintained in accordance with Sec. 835.703(b)
and the unrecorded internal dose estimated for any individual in a year
does not exceed 50 percent of the applicable monitoring threshold at
Sec. 835.402(c).
(c) * * *
(3) * * *
(i) The effective dose from external sources of radiation (deep
equivalent dose may be used as effective dose for external exposure);
(ii) The lens of the eye equivalent dose;
(iii) The shallow equivalent dose to the skin; and
(iv) The shallow equivalent dose to the extremities.
(4) * * *
(i) Committed effective dose;
(ii) Committed equivalent dose to any organ or tissue of concern;
and
(iii) * * *
(5) * * *
(i) Total effective dose in a year;
(ii) For any organ or tissue assigned an internal dose during the
year, the sum of the deep equivalent dose from external exposures and
the committed equivalent dose to that organ or tissue; and
(iii) Cumulative total effective dose.
(6) Include the equivalent dose to the embryo/fetus of a declared
pregnant worker.
* * * * *
25. Section 835.901 is amended by revising paragraph (b)
introductory text:
Sec. 835.901 Radiation safety training.
* * * * *
(b) Each individual shall demonstrate knowledge of the radiation
safety training topics established in Sec. 835.901(c), commensurate
with the hazards in the area and required controls, by successful
completion of applied training, an examination and performance
demonstrations:
* * * * *
Sec. 835.1001 [Amended]
26. Section 835.1001 is amended:
a. In paragraph (a), first sentence, remove ``physical design
features and administrative control'' and add in its place
``engineering and administrative controls.''
b. In paragraph (b), remove ``physical design features is'' and add
in its place ``engineering controls are''.
Sec. 835.1003 [Amended]
27. Section 835.1003 is amended in the introductory text by
removing ``physical design features and administrative controls'' and
add in its place ``engineering and administrative controls''.
Sec. 835.1301 [Amended]
28. In Sec. 835.1301, paragraph (d) is amended by removing ``after
a dose was received'' and adding in its place ``which have been
suspended as a result of a dose''.
29. Appendix A to part 835 is revised to read as follows:
Appendix A to Part 835--Derived Air Concentrations (DAC) for
Controlling Radiation Exposure to Workers at DOE Facilities
The data presented in this appendix A are to be used for
controlling individual internal doses in accordance with Sec.
835.209, identifying the need for air monitoring in accordance with
Sec. 835.403, and identifying and posting airborne radioactivity
areas in accordance with Sec. 835.603(d).
The DAC values are given for individual radionuclides. For known
mixtures of radionuclides, determine the sum of the ratio of the
observed concentration of a particular radionuclide and its
corresponding DAC for all radionuclides in the mixture. If this sum
exceeds unity (1), then the DAC has been exceeded. For unknown
radionuclides, the most restrictive DAC (lowest value) for those
isotopes not known to be absent shall be used.
The derived air concentrations (DAC) for limiting radiation
exposures through inhalation of radionuclides by workers are listed
in this appendix. The values are based on either a stochastic
(committed effective dose) dose limit of 5 rems (0.05 Sv) or a
nonstochastic (organ) dose limit of 50 rems (0.5 Sv) per year,
whichever is more limiting.
Note: the 15 rems (0.15 Sv) dose limit for the lens of the eye
does not appear as a critical organ dose limit.
The columns in this appendix contain the following information:
(1) Radionuclide; (2) inhaled air DAC for type F (fast), type M
(moderate), and type S (slow) materials in units of [mu]Ci/ml; (3)
inhaled air DAC for type F (fast), type M (moderate), and type S
(slow) materials in units of Bq/m\3\; (4) an indication of whether
or not the DAC for each class is controlled by the stochastic
(effective dose) or nonstochastic (tissue) dose. The material types
(F, M, and S) have been established to describe the absorption rate
of the materials from the respiratory tract into the blood. The
range of half-times for the absorption rates correspond to: Type F,
100% at 10 minute; Type M, 10% at 10 minute and 90% at 140 day; and
Type S 0.1% at 10 minute and 99.9% at 7000 day. The DACs are listed
by radionuclide, in order of increasing atomic mass, and are based
on the assumption that the particle size distribution of 5 [mu]m is
used. For situations where the particle size distribution is known
to differ significantly from 5 [mu]m, appropriate corrections may be
made to both the estimated dose to workers and the DACs.
[[Page 46011]]
--------------------------------------------------------------------------------------------------------------------------------------------------------
Material type 3 Material type 3 Stochastic or
------------------------------------------------------------------------------------------------------ organ 1
Radionuclide [mu]Ci/ml Bq/m 3 ------------------
------------------------------------------------------------------------------------------------------
F M S F M S (F/M/S)
--------------------------------------------------------------------------------------------------------------------------------------------------------
H-3 (Water) \2\................ 2.E-05 2.E-05 2.E-05 7.E+05 7.E+05 7.E+05 St/St/St
H-3 (Elemental) \2\............ 2.E-01 2.E-01 2.E-01 9.E+09 9.E+09 9.E+09 St/St/St
Tritiated Particulate Aerosol 1.E-05 6.E-06 2.E-06 3.E+05 2.E+05 8.E+04 St/St/St
and Organically Bound H-3
(Insoluble) \4\.
Organically Bound H-3 (Soluble) 1.E-05 1.E-05 1.E-05 5.E+05 5.E+05 5.E+05 St/St/St
Be-7........................... - 1.E-05 1.E-05 - 4.E+05 4.E+05 /St/St
Be-10.......................... - 8.E-08 2.E-08 - 3.E+03 1.E+03 /St/St
C-11 (Vapor) \2\............... - 1.E-04 - - 6.E+06 - /St/
C-11 (CO) \2\.................. 4.E-04 4.E-04 4.E-04 1.E+07 1.E+07 1.E+07 St/St/St
C-11 (CO2) \2\................. 2.E-04 2.E-04 2.E-04 9.E+06 9.E+06 9.E+06 St/St/St
C-14 (Vapor) \2\............... - 9.E-07 - - 3.E+04 - /St/
C-14 (CO) \2\.................. 7.E-04 7.E-04 7.E-04 2.E+07 2.E+07 2.E+07 St/St/St
C-14 (CO2) \2\................. 8.E-05 8.E-05 8.E-05 3.E+06 3.E+06 3.E+06 St/St/St
F-18........................... 4.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Na-22.......................... 2.E-07 - - 1.E+04 - - E/ /
Na-24.......................... 4.E-07 - - 1.E+04 - - ET/ /
Mg-28.......................... 3.E-07 3.E-07 - 1.E+04 1.E+04 - ET/St/
Al-26.......................... 4.E-08 4.E-08 - 1.E+03 1.E+03 - St/St/
Si-31.......................... 9.E-06 5.E-06 5.E-06 3.E+05 1.E+05 1.E+05 ET/St/St
Si-32.......................... 1.E-07 5.E-08 1.E-08 5.E+03 2.E+03 3.E+02 St/St/St
P-32........................... 5.E-07 1.E-07 - 1.E+04 7.E+03 - St/St/
P-33........................... 4.E-06 4.E-07 - 1.E+05 1.E+04 - St/St/
S-35 (Vapor)................... - 4.E-06 - - 1.E+05 - /St/
S-35........................... 7.E-06 5.E-07 - 2.E+05 1.E+04 - St/St/
Cl-36.......................... 1.E-06 1.E-07 - 4.E+04 4.E+03 - St/St/
Cl-38.......................... 7.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
Cl-39.......................... 2.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
K-40........................... 1.E-07 - - 6.E+03 - - St/ /
K-42........................... 2.E-06 - - 1.E+05 - - E/ /
K-43........................... 9.E-07 - - 3.E+04 - - ET/ /
K-44........................... 8.E-06 - - 2.E+05 - - ET/ /
K-45........................... 9.E-06 - - 3.E+05 - - ET/ /
Ca-41.......................... - 2.E-06 - - 8.E+04 - /BS/
Ca-45.......................... - 2.E-07 - - 9.E+03 - /St/
Ca-47.......................... - 2.E-07 - - 9.E+03 - /St/
Sc-43.......................... - - 2.E-06 - - 7.E+04 / /ET
Sc-44m......................... - - 2.E-07 - - 1.E+04 / /St
Sc-44.......................... - - 1.E-06 - - 4.E+04 / /ET
Sc-46.......................... - - 1.E-07 - - 4.E+03 / /St
Sc-47.......................... - - 7.E-07 - - 2.E+04 / /St
Sc-48.......................... - - 2.E-07 - - 1.E+04 / /ET
Sc-49.......................... - - 8.E-06 - - 3.E+05 / /ET
Ti-44.......................... 7.E-09 2.E-08 9.E-09 2.E+02 7.E+02 3.E+02 St/St/St
Ti-45.......................... 3.E-06 2.E-06 2.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
V-47........................... 8.E-06 6.E-06 - 3.E+05 2.E+05 - ET/ET/
V-48........................... 2.E-07 2.E-07 - 9.E+03 7.E+03 - ET/St/
V-49........................... 1.E-05 2.E-05 - 7.E+05 9.E+05 - BS/St/
Cr-48.......................... 2.E-06 2.E-06 2.E-06 8.E+04 8.E+04 8.E+04 ET/ET/ET
Cr-49.......................... 7.E-06 5.E-06 5.E-06 2.E+05 2.E+05 2.E+05 ET/ET/ET
Cr-51.......................... 1.E-05 1.E-05 1.E-05 6.E+05 6.E+05 5.E+05 St/St/St
Mn-51.......................... 7.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
Mn-52m......................... 7.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
Mn-52.......................... 2.E-07 2.E-07 - 8.E+03 8.E+03 - ET/ET/
Mn-53.......................... 5.E-06 1.E-05 - 2.E+05 5.E+05 - BS/St/
Mn-54.......................... 5.E-07 4.E-07 - 1.E+04 1.E+04 - St/St/
Mn-56.......................... 2.E-06 2.E-06 - 9.E+04 8.E+04 - ET/ET/
Fe-52.......................... 6.E-07 5.E-07 - 2.E+04 2.E+04 - ET/E/
Fe-55.......................... 6.E-07 1.E-06 - 2.E+04 6.E+04 - St/St/
Fe-59.......................... 1.E-07 1.E-07 - 6.E+03 6.E+03 - St/St/
Fe-60.......................... 1.E-09 4.E-09 - 6.E+01 1.E+02 - St/St/
Co-55.......................... - 5.E-07 5.E-07 - 2.E+04 2.E+04 /ET/ET
Co-56.......................... - 1.E-07 1.E-07 - 5.E+03 4.E+03 /St/St
Co-57.......................... - 1.E-06 9.E-07 - 5.E+04 3.E+04 /St/St
Co-58m......................... - 3.E-05 3.E-05 - 1.E+06 1.E+06 /St/St
Co-58.......................... - 4.E-07 3.E-07 - 1.E+04 1.E+04 /St/St
Co-60m......................... - 4.E-04 4.E-04 - 1.E+07 1.E+07 /St/St
Co-60.......................... - 7.E-08 3.E-08 - 2.E+03 1.E+03 /St/St
Co-61.......................... - 6.E-06 6.E-06 - 2.E+05 2.E+05 /ET/ET
Co-62m......................... - 7.E-06 6.E-06 - 2.E+05 2.E+05 /ET/ET
Ni-56 (Inorg).................. 4.E-07 4.E-07 - 1.E+04 1.E+04 - ET/ET/
[[Page 46012]]
Ni-56 (Carbonyl)............... - 4.E-07 - - 1.E+04 - /St/
Ni-57 (Inorg).................. 5.E-07 5.E-07 - 2.E+04 2.E+04 - ET/ET/
Ni-57 (Carbonyl)............... - 7.E-07 - - 2.E+04 - /ET/
Ni-59 (Inorg).................. 2.E-06 5.E-06 - 9.E+04 2.E+05 - St/St/
Ni-59 (Carbonyl)............... - 6.E-07 - - 2.E+04 - /St/
Ni-63 (Inorg).................. 1.E-06 1.E-06 - 4.E+04 6.E+04 - St/St/
Ni-63 (Carbonyl)............... - 2.E-07 - - 1.E+04 - /St/
Ni-65 (Inorg).................. 5.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
Ni-65 (Carbonyl)............... - 8.E-07 - - 3.E+04 - /ET/
Ni-66 (Inorg).................. 7.E-07 2.E-07 - 2.E+04 1.E+04 - St/St/
Ni-66 (Carbonyl)............... - 2.E-07 - - 1.E+04 - /ET/
Cu-60.......................... 5.E-06 4.E-06 4.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Cu-61.......................... 3.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Cu-64.......................... 4.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/E/E
Cu-67.......................... 2.E-06 1.E-06 9.E-07 8.E+04 3.E+04 3.E+04 ET/St/St
Zn-62.......................... - - 8.E-07 - - 3.E+04 / /St
Zn-63.......................... - - 5.E-06 - - 2.E+05 / /ET
Zn-65.......................... - - 2.E-07 - - 7.E+03 / /St
Zn-69m......................... - - 1.E-06 - - 6.E+04 / /St
Zn-69.......................... - - 7.E-06 - - 2.E+05 / /ET
Zn-71m......................... - - 1.E-06 - - 5.E+04 / /ET
Zn-72.......................... - - 3.E-07 - - 1.E+04 / /St
Ga-65.......................... 1.E-05 9.E-06 - 4.E+05 3.E+05 - ET/ET/
Ga-66.......................... 8.E-07 7.E-07 - 3.E+04 2.E+04 - ET/St/
Ga-67.......................... 3.E-06 2.E-06 - 1.E+05 7.E+04 - ET/St/
Ga-68.......................... 6.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
Ga-70.......................... 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Ga-72.......................... 5.E-07 5.E-07 - 2.E+04 2.E+04 - ET/ET/
Ga-73.......................... 4.E-06 2.E-06 - 1.E+05 1.E+05 - ET/St/
Ge-66.......................... 2.E-06 2.E-06 - 9.E+04 9.E+04 - ET/ET/
Ge-67.......................... 1.E-05 7.E-06 - 3.E+05 2.E+05 - ET/ET/
Ge-68.......................... 6.E-07 7.E-08 - 2.E+04 2.E+03 - ET/St/
Ge-69.......................... 1.E-06 1.E-06 - 3.E+04 3.E+04 - ET/ET/
Ge-71.......................... 5.E-05 5.E-05 - 2.E+06 1.E+06 - ET/E/
Ge-75.......................... 1.E-05 7.E-06 - 4.E+05 2.E+05 - ET/ET/
Ge-77.......................... 1.E-06 1.E-06 - 4.E+04 4.E+04 - ET/ET/
Ge-78.......................... 3.E-06 3.E-06 - 1.E+05 1.E+05 - ET/ET/
As-69.......................... - 9.E-06 - - 3.E+05 - /ET/
As-70.......................... - 2.E-06 - - 8.E+04 - /ET/
As-71.......................... - 1.E-06 - - 4.E+04 - /St/
As-72.......................... - 4.E-07 - - 1.E+04 - /St/
As-73.......................... - 8.E-07 - - 3.E+04 - /St/
As-74.......................... - 3.E-07 - - 1.E+04 - /St/
As-76.......................... - 6.E-07 - - 2.E+04 - /St/
As-77.......................... - 1.E-06 - - 4.E+04 - /St/
As-78.......................... - 3.E-06 - - 1.E+05 - /ET/
Se-70.......................... 2.E-06 2.E-06 - 1.E+05 9.E+04 - ET/ET/
Se-73m......................... 1.E-05 1.E-05 - 5.E+05 4.E+05 - ET/ET/
Se-73.......................... 1.E-06 1.E-06 - 6.E+04 5.E+04 - ET/ET/
Se-75.......................... 4.E-07 3.E-07 - 1.E+04 1.E+04 - St/St/
Se-79.......................... 3.E-07 1.E-07 - 1.E+04 6.E+03 - K/St/
Se-81m......................... 1.E-05 6.E-06 - 3.E+05 2.E+05 - ET/ET/
Se-81.......................... 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Se-83.......................... 6.E-06 5.E-06 - 2.E+05 1.E+05 - ET/ET/
Br-74m......................... 3.E-06 2.E-06 - 1.E+05 1.E+05 - ET/ET/
Br-74.......................... 4.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
Br-75.......................... 4.E-06 3.E-06 - 1.E+05 1.E+05 - ET/ET/
Br-76.......................... 5.E-07 5.E-07 - 2.E+04 2.E+04 - ET/ET/
Br-77.......................... 2.E-06 2.E-06 - 7.E+04 7.E+04 - ET/ET/
Br-80m......................... 6.E-06 5.E-06 - 2.E+05 2.E+05 - ET/St/
Br-80.......................... 3.E-05 2.E-05 - 1.E+06 7.E+05 - ET/ET/
Br-82.......................... 3.E-07 3.E-07 - 1.E+04 1.E+04 - ET/ET/
Br-83.......................... 9.E-06 6.E-06 - 3.E+05 2.E+05 - ET/ET/
Br-84.......................... 7.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
Rb-79.......................... 8.E-06 - - 2.E+05 - - ET/ /
Rb-81m......................... 1.E-05 - - 6.E+05 - - ET/ /
Rb-81.......................... 2.E-06 - - 1.E+05 - - ET/ /
Rb-82m......................... 8.E-07 - - 3.E+04 - - ET/ /
Rb-83.......................... 5.E-07 - - 2.E+04 - - St/ /
Rb-84.......................... 3.E-07 - - 1.E+04 - - St/ /
[[Page 46013]]
Rb-86.......................... 4.E-07 - - 1.E+04 - - St/ /
Rb-87.......................... 7.E-07 - - 2.E+04 - - St/ /
Rb-88.......................... 1.E-05 - - 5.E+05 - - ET/ /
Rb-89.......................... 1.E-05 - - 3.E+05 - - ET/ /
Sr-80.......................... 3.E-06 - 2.E-06 1.E+05 - 9.E+04 ET/ /St
Sr-81.......................... 7.E-06 - 5.E-06 2.E+05 - 2.E+05 ET/ /ET
Sr-82.......................... 1.E-07 - 7.E-08 6.E+03 - 2.E+03 St/ /St
Sr-83.......................... 1.E-06 - 9.E-07 3.E+04 - 3.E+04 ET/ /ET
Sr-85m......................... 4.E-05 - 3.E-05 1.E+06 - 1.E+06 ET/ /ET
Sr-85.......................... 1.E-06 - 8.E-07 3.E+04 - 3.E+04 St/ /St
Sr-87m......................... 1.E-05 - 9.E-06 4.E+05 - 3.E+05 ET/ /ET
Sr-89.......................... 4.E-07 - 1.E-07 1.E+04 - 3.E+03 St/ /St
Sr-90.......................... 1.E-08 - 7.E- 4.E+02 - 2.E+02 BS/ /St
Sr-91.......................... 1.E-06 - 9.E-07 5.E+04 - 3.E+04 ET/ /St
Sr-92.......................... 2.E-06 - 1.E-06 8.E+04 - 6.E+04 ET/ /St
Y-86m.......................... - 7.E-06 6.E-06 - 2.E+05 2.E+05 /ET/ET
Y-86........................... - 4.E-07 4.E-07 - 1.E+04 1.E+04 /ET/ET
Y-87........................... - 9.E-07 8.E-07 - 3.E+04 3.E+04 /ET/ET
Y-88........................... - 1.E-07 1.E-07 - 6.E+03 6.E+03 /St/St
Y-90m.......................... - 4.E-06 4.E-06 - 1.E+05 1.E+05 /St/St
Y-90........................... - 3.E-07 3.E-07 - 1.E+04 1.E+04 /St/St
Y-91m.......................... - 2.E-05 2.E-05 - 7.E+05 7.E+05 /ET/ET
Y-91........................... - 1.E-07 9.E-08 - 4.E+03 3.E+03 /St/St
Y-92........................... - 2.E-06 2.E-06 - 7.E+04 7.E+04 /St/St
Y-93........................... - 9.E-07 9.E-07 - 3.E+04 3.E+04 /St/St
Y-94........................... - 8.E-06 8.E-06 - 3.E+05 3.E+05 /ET/ET
Y-95........................... - 1.E-05 1.E-05 - 4.E+05 4.E+05 /ET/ET
Zr-86.......................... 5.E-07 5.E-07 5.E-07 2.E+04 2.E+04 2.E+04 T/ET/ET
Zr-88.......................... 1.E-07 3.E-07 3.E-07 5.E+03 1.E+04 1.E+04 St/St/St
Zr-89.......................... 6.E-07 6.E-07 6.E-07 2.E+04 2.E+04 2.E+04 ET/ET/ET
Zr-93.......................... 3.E-09 1.E-08 1.E-07 1.E+02 6.E+02 5.E+03 BS/BS/BS
Zr-95.......................... 9.E-08 1.E-07 1.E-07 3.E+03 5.E+03 4.E+03 BS/St/St
Zr-97.......................... 7.E-07 4.E-07 4.E-07 2.E+04 1.E+04 1.E+04 ET/St/St
Nb-88.......................... - 5.E-06 5.E-06 - 1.E+05 1.E+05 /ET/ET
Nb-89 (66 min)................. - 3.E-06 3.E-06 - 1.E+05 1.E+05 /ET/ET
Nb-89 (122 min)................ - 2.E-06 2.E-06 - 1.E+05 1.E+05 /ET/ET min)
Nb-90.......................... - 3.E-07 3.E-07 - 1.E+04 1.E+04 /ET/ET
Nb-93m......................... - 1.E-06 6.E-07 - 7.E+04 2.E+04 /St/St
Nb-94.......................... - 7.E-08 2.E-08 - 2.E+03 8.E+02 /St/St
Nb-95m......................... - 7.E-07 6.E-07 - 2.E+04 2.E+04 /St/St
Nb-95.......................... - 4.E-07 4.E-07 - 1.E+04 1.E+04 /St/St
Nb-96.......................... - 4.E-07 4.E-07 - 1.E+04 1.E+04 /ET/ET
Nb-97.......................... - 5.E-06 5.E-06 - 1.E+05 1.E+05 /ET/ET
Nb-98.......................... - 3.E-06 3.E-06 - 1.E+05 .E+05 /ET/ET
Mo-90.......................... 8.E-07 - 7.E-07 3.E+04 - 2.E+04 ET/ /ET
Mo-93m......................... 1.E-06 - 1.E-06 3.E+04 - 3.E+04 ET/ /ET
Mo-93.......................... 2.E-07 - 4.E-07 7.E+03 - 1.E+04 BS/ /St
Mo-99.......................... 1.E-06 - 5.E-07 5.E+04 - 1.E+04 E/ /St
Mo-101......................... 8.E-06 - 6.E-06 3.E+05 - 2.E+05 ET/ /ET
Tc-93m......................... 8.E-06 7.E-06 - 3.E+05 2.E+05 - ET/ET/
Tc-93.......................... 3.E-06 3.E-06 - 1.E+05 1.E+05 - ET/ET/
Tc-94m......................... 5.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
Tc-94.......................... 1.E-06 1.E-06 - 4.E+04 3.E+04 - ET/ET/
Tc-95m......................... 8.E-07 6.E-07 - 3.E+04 2.E+04 - ET/St/
Tc-95.......................... 1.E-06 1.E-06 - 5.E+04 5.E+04 - ET/ET/
Tc-96m......................... 2.E-05 2.E-05 - 1.E+06 1.E+06 - ET/ET/
Tc-96.......................... 3.E-07 3.E-07 - 1.E+04 1.E+04 - ET/ET/
Tc-97m........................ 1.E-06 2.E-07 - 5.E+04 7.E+03 - St/St/
Tc-97.......................... 4.E-06 3.E-06 - 1.E+05 1.E+05 - ET/St/
Tc-98.......................... 3.E-07 9.E-08 - 1.E+04 3.E+03 - St/St/
Tc-99m......................... 1.E-05 1.E-05 - 5.E+05 4.E+05 - ET/ET/
Tc-99.......................... 1.E-06 1.E-07 - 5.E+04 6.E+03 - St/St/
Tc-101......................... 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Tc-104......................... 9.E-06 7.E-06 - 3.E+05 2.E+05 - ET/ET/
Ru-94.......................... 5.E-06 5.E-06 5.E-06 2.E+05 1.E+05 1.E+05 ET/ET/ET
Ru-97.......................... 2.E-06 2.E-06 2.E-06 8.E+04 8.E+04 8.E+04 ET/ET/ET
Ru-103......................... 8.E-07 2.E-07 2.E-07 3.E+04 1.E+04 9.E+03 St/St/St
Ru-105......................... 2.E-06 2.E-06 2.E-06 9.E+04 8.E+04 8.E+04 ET/ET/ET
Ru-106......................... 5.E-08 3.E-08 1.E-08 2.E+03 1.E+03 5.E+02 St/St/St
[[Page 46014]]
Rh-99m......................... 3.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Rh-99.......................... 8.E-07 6.E-07 6.E-07 3.E+04 2.E+04 2.E+04 ET/St/St
Rh-100......................... 5.E-07 5.E-07 5.E-07 1.E+04 1.E+04 1.E+04 ET/ET/ET
Rh-101m........................ 1.E-06 1.E-06 1.E-06 6.E+04 6.E+04 6.E+04 ET/ET/ET
Rh-101......................... 3.E-07 3.E-07 1.E-07 1.E+04 1.E+04 6.E+03 St/St/St
Rh-102m........................ 2.E-07 2.E-07 1.E-07 1.E+04 7.E+03 4.E+03 St/St/St
Rh-102......................... 6.E-08 1.E-07 6.E-08 2.E+03 4.E+03 2.E+03 St/St/St
Rh-103m........................ 4.E-04 2.E-04 2.E-04 1.E+07 8.E+06 8.E+06 St/St/St
Rh-105......................... 3.E-06 1.E-06 1.E-06 1.E+05 5.E+04 4.E+04 ET/St/St
Rh-106m........................ 1.E-06 1.E-06 1.E-06 6.E+04 5.E+04 5.E+04 ET/ET/ET
Rh-107......................... 1.E-05 9.E-06 9.E-06 5.E+05 3.E+05 3.E+05 ET/ET/ET
Pd-100......................... 5.E-07 5.E-07 5.E-07 2.E+04 2.E+04 2.E+04 ET/ET/ET
Pd-101......................... 3.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Pd-103......................... 4.E-06 1.E-06 1.E-06 1.E+05 6.E+04 7.E+04 E/St/St
Pd-107......................... 1.E-05 1.E-05 1.E-06 5.E+05 4.E+05 7.E+04 K/St/St
Pd-109......................... 2.E-06 1.E-06 1.E-06 9.E+04 4.E+04 4.E+04 St/St/St
Ag-102......................... 9.E-06 7.E-06 7.E-06 3.E+05 2.E+05 2.E+05 ET/ET/ET
Ag-103......................... 8.E-06 7.E-06 7.E-06 3.E+05 2.E+05 2.E+05 ET/ET/ET
Ag-104m........................ 8.E-06 6.E-06 6.E-06 2.E+05 2.E+05 2.E+05 ET/ET/ET
Ag-104......................... 3.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Ag-105......................... 7.E-07 8.E-07 7.E-07 2.E+04 2.E+04 2.E+04 St/St/St
Ag-106m........................ 2.E-07 2.E-07 2.E-07 9.E+03 9.E+03 9.E+03 ET/ET/ET
Ag-106......................... 1.E-05 1.E-05 1.E-05 5.E+05 4.E+05 4.E+05 ET/ET/ET
Ag-108m........................ 7.E-08 1.E-07 2.E-08 2.E+03 4.E+03 1.E+03 St/St/St
Ag-110m........................ 8.E-08 9.E-08 7.E-08 3.E+03 3.E+03 2.E+03 St/St/St
Ag-111......................... 9.E-07 3.E-07 3.E-07 3.E+04 1.E+04 1.E+04 St/St/St
Ag-112......................... 4.E-06 2.E-06 2.E-06 1.E+05 8.E+04 8.E+04 E/St/St
Ag-115......................... 1.E-05 8.E-06 8.E-06 4.E+05 3.E+05 3.E+05 ET/ET/ET
Cd-104......................... 4.E-06 4.E-06 4.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Cd-107......................... 5.E-06 5.E-06 4.E-06 2.E+05 1.E+05 1.E+05 ET/ET/ET
Cd-109......................... 2.E-08 9.E-08 1.E-07 9.E+02 3.E+03 4.E+03 K/K/St
Cd-113m........................ 1.E-09 6.E-09 1.E-08 6.E+01 2.E+02 6.E+02 K/K/K
Cd-113......................... 1.E-09 5.E-09 1.E-08 5.E+01 2.E+02 5.E+02 K/K/K
Cd-115m........................ 3.E-08 1.E-07 1.E-07 1.E+03 3.E+03 3.E+03 K/St/St
Cd-115......................... 9.E-07 4.E-07 4.E-07 3.E+04 1.E+04 1.E+04 K/St/St
Cd-117m........................ 1.E-06 1.E-06 1.E-06 4.E+04 4.E+04 4.E+04 ET/ET/ET
Cd-117......................... 2.E-06 2.E-06 2.E-06 8.E+04 7.E+04 7.E+04 ET/ET/ET
In-109......................... 4.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
In-110 (69 min)................ 5.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
In-110 (5 h)................... 9.E-07 9.E-07 - 3.E+04 3.E+04 - ET/ET/
In-111......................... 1.E-06 1.E-06 - 5.E+04 5.E+04 - ET/ET/
In-112......................... 2.E-05 1.E-05 - 9.E+05 6.E+05 - ET/ET/
In-113m........................ 1.E-05 1.E-05 - 4.E+05 3.E+05 - ET/ET/
In-114m........................ 5.E-08 9.E-08 - 1.E+03 3.E+03 - St/St/
In-115m........................ 6.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
In-115......................... 1.E-09 5.E-09 - 4.E+01 1.E+02 - St/St/
In-116m........................ 4.E-06 3.E-06 - 1.E+05 1.E+05 - ET/ET/
In-117m........................ 5.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
In-117......................... 7.E-06 5.E-06 - 2.E+05 2.E+05 - ET/ET/
In-119m........................ 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Sn-110......................... 1.E-06 1.E-06 - 6.E+04 6.E+04 - ET/ET/
Sn-111......................... 1.E-05 1.E-05 - 6.E+05 5.E+05 - ET/ET/
Sn-113......................... 7.E-07 2.E-07 - 2.E+04 1.E+04 - St/St/
Sn-117m........................ 8.E-07 2.E-07 - 3.E+04 9.E+03 - BS/St/
Sn-119m........................ 1.E-06 3.E-07 - 5.E+04 1.E+04 - St/St/
Sn-121m........................ 5.E-07 1.E-07 - 2.E+04 6.E+03 - St/St/
Sn-121......................... 4.E-06 2.E-06 - 1.E+05 7.E+04 - ET/St/
Sn-123m........................ 1.E-05 7.E-06 - 4.E+05 2.E+05 - ET/ET/
Sn-123......................... 3.E-07 1.E-07 - 1.E+04 3.E+03 - St/St/
Sn-125......................... 4.E-07 2.E-07 - 1.E+04 7.E+03 - St/St/
Sn-126......................... 4.E-08 3.E-08 - 1.E+03 1.E+03 - St/St/
Sn-127......................... 2.E-06 2.E-06 - 9.E+04 7.E+04 - ET/ET/
Sn-128......................... 2.E-06 2.E-06 - 1.E+05 8.E+04 - ET/ET/
Sb-115......................... 1.E-05 1.E-05 - 5.E+05 4.E+05 - ET/ET/
Sb-116m........................ 3.E-06 2.E-06 - 1.E+05 1.E+05 - ET/ET/
Sb-116......................... 1.E-05 1.E-05 - 4.E+05 3.E+05 - ET/ET/
Sb-117......................... 1.E-05 1.E-05 - 4.E+05 3.E+05 - ET/ET/
Sb-118m........................ 1.E-06 1.E-06 - 4.E+04 4.E+04 - ET/ET/
Sb-119......................... 6.E-06 6.E-06 - 2.E+05 2.E+05 - ET/ET/
Sb-120 (16 min)................ 2.E-05 2.E-05 - 1.E+06 7.E+05 - ET/ET/
[[Page 46015]]
Sb-120 (6 d)................... 3.E-07 3.E-07 - 1.E+04 1.E+04 - ET/ET/
Sb-122......................... 8.E-07 4.E-07 - 3.E+04 1.E+04 - St/St/
Sb-124m........................ 4.E-05 3.E-05 - 1.E+06 1.E+06 - ET/ET/
Sb-124......................... 2.E-07 1.E-07 - 1.E+04 4.E+03 - St/St/
Sb-125......................... 2.E-07 1.E-07 - 7.E+03 6.E+03 - BS/St/
Sb-126m........................ 1.E-05 7.E-06 - 3.E+05 2.E+05 - ET/ET/
Sb-126......................... 2.E-07 1.E-07 - 9.E+03 6.E+03 - ET/St/
Sb-127......................... 7.E-07 3.E-07 - 2.E+04 1.E+04 - E/St/
Sb-128 (9 h)................... 5.E-07 5.E-07 - 2.E+04 2.E+04 - ET/ET/
Sb-128 (10 min)................ 1.E-05 9.E-06 - 4.E+05 3.E+05 - ET/ET/
Sb-129......................... 1.E-06 1.E-06 - 6.E+04 5.E+04 - ET/ET/
Sb-130......................... 3.E-06 2.E-06 - 1.E+05 1.E+05 - ET/ET/
Sb-131......................... 6.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
Te-116 (Vapor)................. - 6.E-06 - - 2.E+05 - /St/
Te-116......................... 2.E-06 2.E-06 - 8.E+04 7.E+04 - ET/ET/
Te-121m (Vapor)................ - 4.E-08 - - 1.E+03 - /BS/
Te-121m........................ 1.E-07 1.E-07 - 4.E+03 5.E+03 - BS/St/
Te-121 (Vapor)................. - 1.E-06 - - 4.E+04 - /St/
Te-121......................... 1.E-06 1.E-06 - 3.E+04 3.E+04 - ET/ET/
Te-123m (Vapor)................ - 5.E-08 - - 2.E+03 - /BS/
Te-123m........................ 1.E-07 1.E-07 - 4.E+03 6.E+03 - BS/St/
Te-123 (Vapor)................. - 1.E-08 - - 4.E+02 - /BS/
Te-123......................... 2.E-08 5.E-08 - 1.E+03 1.E+03 - BS/BS/
Te-125m (Vapor)................ - 1.E-07 - - 3.E+03 - /BS/
Te-125m........................ 2.E-07 1.E-07 - 9.E+03 7.E+03 - BS/St/
Te-127m (Vapor)................ - 6.E-08 - - 2.E+03 - /BS/
Te-127m........................ 1.E-07 9.E-08 - 5.E+03 3.E+03 - BS/St/
Te-127 (Vapor)................. - 7.E-06 - - 2.E+05 - /St/
Te-127......................... 5.E-06 3.E-06 - 2.E+05 1.E+05 - ET/St/
Te-129m (Vapor)................ - 1.E-07 - - 5.E+03 - /St/
Te-129m........................ 3.E-07 1.E-07 - 1.E+04 3.E+03 - St/St/
Te-129 (Vapor)................. - 1.E-05 - - 5.E+05 - /St/
Te-129......................... 1.E-05 7.E-06 - 4.E+05 2.E+05 - ET/ET/
Te-131m (Vapor)................ - 1.E-07 - - 5.E+03 - /T/
Te-131m........................ 3.E-07 3.E-07 - 1.E+04 1.E+04 - T/St/
Te-131 (Vapor)................. - 6.E-06 - - 2.E+05 - /T/
Te-131......................... 1.E-05 7.E-06 - 4.E+05 2.E+05 - ET/ET/
Te-132 (Vapor)................. - 7.E-08 - - 2.E+03 - /T/
Te-132......................... 1.E-07 1.E-07 - 6.E+03 6.E+03 - T/St/
Te-133m (Vapor)................ - 1.E-06 - - 6.E+04 - /T/
Te-133m........................ 3.E-06 2.E-06 - 1.E+05 1.E+05 - T/ET/
Te-133 (Vapor)................. - 7.E-06 - - 2.E+05 - /T/
Te-133......................... 1.E-05 9.E-06 - 4.E+05 3.E+05 - ET/ET/
Te-134 (Vapor)................. - 6.E-06 - - 2.E+05 - /St/
Te-134......................... 3.E-06 2.E-06 - 1.E+05 1.E+05 - ET/ET/
I-120m (Methyl)................ 4.E-06 - - 1.E+05 - - T/ /
I-120m (Vapor)................. - 3.E-06 - - 1.E+05 - /St/
I-120m......................... 2.E-06 - - 8.E+04 - - ET/ /
I-120 (Methyl)................. 1.E-06 - - 6.E+04 - - T/ /
I-120 (Vapor).................. - 1.E-06 - - 5.E+04 - /T/
I-120.......................... 2.E-06 - - 1.E+05 - - E/ /
I-121 (Methyl)................. 5.E-06 - - 2.E+05 - - T/ /
I-121 (Vapor).................. - 4.E-06 - - 1.E+05 - /T/
I-121.......................... 8.E-06 - - 3.E+05 - - T/ /
I-123 (Methyl)................. 1.E-06 - - 7.E+04 - - T/ /
I-123 (Vapor).................. - 1.E-06 - - 5.E+04 - /T/
I-123.......................... 2.E-06 - - 1.E+05 - - T/ /
I-124 (Methyl)................. 3.E-08 - - 1.E+03 - - T/ /
I-124 (Vapor).................. - 2.E-08 - - 9.E+02 - /T/
I-124.......................... 4.E-08 - - 1.E+03 - - T/ /
I-125 (Methyl)................. 2.E-08 - - 9.E+02 - - T/ /
I-125 (Vapor).................. - 2.E-08 - - 7.E+02 - /T/
I-125.......................... 3.E-08 - - 1.E+03 - - T/ /
I-126 (Methyl)................. 1.E-08 - - 5.E+02 - - T/ /
I-126 (Vapor).................. - 1.E-08 - - 4.E+02 - /T/
I-126.......................... 2.E-08 - - 7.E+02 - - T/ /
I-128 (Methyl)................. 3.E-05 - - 1.E+06 - - T/ /
I-128 (Vapor).................. - 8.E-06 - - 3.E+05 - /St/
I-128.......................... 1.E-05 - - 6.E+05 - - ET/ /
I-129 (Methyl)................. 3.E-09 - - 1.E+02 - - T/ /
[[Page 46016]]
I-129 (Vapor).................. - 2.E-09 - - 1.E+02 - /T/
I-129.......................... 5.E-09 - - 2.E+02 - - T/ /
I-130 (Methyl)................. 2.E-07 - - 7.E+03 - - T/ /
I-130 (Vapor).................. - 1.E-07 - - 6.E+03 - /T/
I-130.......................... 3.E-07 - - 1.E+04 - - T/ /
I-131 (Methyl)................. 1.E-08 - - 6.E+02 - - T/ /
I-131 (Vapor).................. - 1.E-08 - - 5.E+02 - /T/
I-131.......................... 2.E-08 - - 9.E+02 - - T/ /
I-132m (Methyl)................ 1.E-06 - - 7.E+04 - - T/ /
I-132m (Vapor)................. - 1.E-06 - - 6.E+04 - /T/
I-132m......................... 3.E-06 - - 1.E+05 - - T/ /
I-132 (Methyl)................. 1.E-06 - - 6.E+04 - - T/ /
I-132 (Vapor).................. - 1.E-06 - - 5.E+04 - /T/
I-132.......................... 2.E-06 - - 7.E+04 - - T/ /
I-133 (Methyl)................. 9.E-08 - - 3.E+03 - - T/ /
I-133 (Vapor).................. - 7.E-08 - - 2.E+03 - /T/
I-133.......................... 1.E-07 - - 5.E+03 - - T/ /
I-134 (Methyl)................. 8.E-06 - - 2.E+05 - - T/ /
I-134 (Vapor).................. - 3.E-06 - - 1.E+05 - /St/
I-134.......................... 3.E-06 - - 1.E+05 - - ET/ /
I-135 (Methyl)................. 4.E-07 - - 1.E+04 - - T/ /
I-135 (Vapor).................. - 3.E-07 - - 1.E+04 - /T/
I-135.......................... 6.E-07 - - 2.E+04 - - T/ /
Cs-125......................... 1.E-05 - - 4.E+05 - - ET/ /
Cs-127......................... 4.E-06 - - 1.E+05 - - ET/ /
Cs-129......................... 2.E-06 - - 9.E+04 - - ET/ /
Cs-130......................... 1.E-05 - - 6.E+05 - - ET/ /
Cs-131......................... 7.E-06 - - 2.E+05 - - ET/ /
Cs-132......................... 9.E-07 - - 3.E+04 - - ET/ /
Cs-134m........................ 8.E-06 - - 2.E+05 - - ET/ /
Cs-134......................... 5.E-08 - - 2.E+03 - - St/ /
Cs-135m........................ 8.E-06 - - 2.E+05 - - ET/ /
Cs-135......................... 5.E-07 - - 2.E+04 - - St/ /
Cs-136......................... 2.E-07 - - 1.E+04 - - E/ /
Cs-137......................... 8.E-08 - - 3.E+03 - - St/ /
Cs-138......................... 5.E-06 - - 2.E+05 - - ET/ /
Ba-126......................... 4.E-06 - - 1.E+05 - - ET/ /
Ba-128......................... 4.E-07 - - 1.E+04 - - St/ /
Ba-131m........................ 4.E-05 - - 1.E+06 - - ET/ /
Ba-131......................... 1.E-06 - - 4.E+04 - - ET/ /
Ba-133m........................ 2.E-06 - - 7.E+04 - - St/ /
Ba-133......................... 3.E-07 - - 1.E+04 - - St/ /
Ba-135m........................ 2.E-06 - - 9.E+04 - - St/ /
Ba-139......................... 1.E-05 - - 3.E+05 - - St/ /
Ba-140......................... 3.E-07 - - 1.E+04 - - St/ /
Ba-141......................... 1.E-05 - - 4.E+05 - - ET/ /
Ba-142......................... 9.E-06 - - 3.E+05 - - ET/ /
La-131......................... 1.E-05 8.E-06 - 4.E+05 3.E+05 - ET/ET/
La-132......................... 1.E-06 1.E-06 - 5.E+04 5.E+04 - ET/ET/
La-135......................... 1.E-05 1.E-05 - 4.E+05 4.E+05 - ET/ET/
La-137......................... 4.E-08 2.E-07 - 1.E+03 8.E+03 - L/L/
La-138......................... 3.E-09 1.E-08 - 1.E+02 4.E+02 - St/St/
La-140......................... 4.E-07 3.E-07 - 1.E+04 1.E+04 - ET/St/
La-141......................... 5.E-06 2.E-06 - 1.E+05 9.E+04 - St/St/
La-142......................... 2.E-06 2.E-06 - 9.E+04 8.E+04 - ET/ET/
La-143......................... 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Ce-134......................... - 3.E-07 3.E-07 - 1.E+04 1.E+04 /St/St
Ce-135......................... - 5.E-07 5.E-07 - 2.E+04 2.E+04 /ET/ET
Ce-137m........................ - 1.E-06 9.E-07 - 3.E+04 3.E+04 /St/St
Ce-137......................... - 1.E-05 1.E-05 - 7.E+05 7.E+05 /ET/ET
Ce-139......................... - 4.E-07 4.E-07 - 1.E+04 1.E+04 /St/St
Ce-141......................... - 2.E-07 1.E-07 - 7.E+03 6.E+03 /St/St
Ce-143......................... - 5.E-07 5.E-07 - 2.E+04 2.E+04 /St/St
Ce-144......................... - 2.E-08 1.E-08 - 9.E+02 7.E+02 /St/St
Pr-136......................... - 1.E-05 1.E-05 - 3.E+05 3.E+05 /ET/ET
Pr-137......................... - 9.E-06 9.E-06 - 3.E+05 3.E+05 /ET/ET
Pr-138m........................ - 2.E-06 2.E-06 - 7.E+04 7.E+04 /ET/ET
Pr-139......................... - 1.E-05 1.E-05 - 5.E+05 5.E+05 /ET/ET
Pr-142m........................ - 6.E-05 5.E-05 - 2.E+06 2.E+06 /St/St
Pr-142......................... - 8.E-07 7.E-07 - 2.E+04 2.E+04 /St/St
[[Page 46017]]
Pr-143......................... - 2.E-07 2.E-07 - 1.E+04 9.E+03 /St/St
Pr-144......................... - 1.E-05 1.E-05 - 4.E+05 4.E+05 /ET/ET
Pr-145......................... - 2.E-06 2.E-06 - 8.E+04 8.E+04 /St/St
Pr-147......................... - 9.E-06 9.E-06 - 3.E+05 3.E+05 /ET/ET
Nd-136......................... - 4.E-06 4.E-06 - 1.E+05 1.E+05 /ET/ET
Nd-138......................... - 1.E-06 1.E-06 - 5.E+04 5.E+04 /St/St
Nd-139m........................ - 1.E-06 1.E-06 - 5.E+04 5.E+04 /ET/ET
Nd-139......................... - 1.E-05 1.E-05 - 6.E+05 6.E+05 /ET/ET
Nd-141......................... - 3.E-05 3.E-05 - 1.E+06 1.E+06 /ET/ET
Nd-147......................... - 2.E-07 2.E-07 - 1.E+04 9.E+03 /St/St
Nd-149......................... - 4.E-06 4.E-06 - 1.E+05 1.E+05 /ET/ET
Nd-151......................... - 9.E-06 9.E-06 - 3.E+05 3.E+05 /ET/ET
Pm-141......................... - 1.E-05 1.E-05 - 4.E+05 4.E+05 /ET/ET
Pm-143......................... - 5.E-07 6.E-07 - 2.E+04 2.E+04 /St/St
Pm-144......................... - 1.E-07 1.E-07 - 3.E+03 5.E+03 /St/St
Pm-145......................... - 1.E-07 4.E-07 - 5.E+03 1.E+04 /BS/St
Pm-146......................... - 4.E-08 6.E-08 - 1.E+03 2.E+03 /St/St
Pm-147......................... - 1.E-07 1.E-07 - 4.E+03 6.E+03 /BS/St
Pm-148m........................ - 1.E-07 1.E-07 - 5.E+03 4.E+03 /St/St
Pm-148......................... - 2.E-07 2.E-07 - 9.E+03 9.E+03 /St/St
Pm-149......................... - 7.E-07 6.E-07 - 2.E+04 2.E+04 /St/St
Pm-150......................... - 2.E-06 2.E-06 - 8.E+04 8.E+04 /ET/ET
Pm-151......................... - 9.E-07 8.E-07 - 3.E+04 3.E+04 /St/St
Sm-141m........................ - 5.E-06 - - 2.E+05 - /ET/
Sm-141......................... - 1.E-05 - - 4.E+05 - /ET/
Sm-142......................... - 4.E-06 - - 1.E+05 - /ET/
Sm-145......................... - 4.E-07 - - 1.E+04 - /BS/
Sm-146......................... - 2.E-11 - - 1.E+00 - /BS/
Sm-147......................... - 2.E-11 - - 1.E+00 - /BS/
Sm-151......................... - 7.E-08 - - 2.E+03 - /BS/
Sm-153......................... - 8.E-07 - - 3.E+04 - St/
Sm-155......................... - 1.E-05 - - 3.E+05 - /ET/
Sm-156......................... - 2.E-06 - - 7.E+04 - /St/
Eu-145......................... - 5.E-07 - - 2.E+04 - /ET/
Eu-146......................... - 3.E-07 - - 1.E+04 - /ET/
Eu-147......................... - 5.E-07 - - 2.E+04 - /St/
Eu-148......................... - 2.E-07 - - 9.E+03 - /St/
Eu-149......................... - 2.E-06 - - 9.E+04 - /St/
Eu-150 (12 h).................. - 2.E-06 - - 7.E+04 - /St/
Eu-150 (34 yr)................. - 1.E-08 - - 6.E+02 - /St/
Eu-152m........................ - 1.E-06 - - 6.E+04 - /St/
Eu-152......................... - 2.E-08 - - 7.E+02 - /St/
Eu-154......................... - 1.E-08 - - 5.E+02 - /St/
Eu-155......................... - 7.E-08 - - 2.E+03 - /BS/
Eu-156......................... - 1.E-07 - - 6.E+03 - /St/
Eu-157......................... - 1.E-06 - - 4.E+04 - /St/
Eu-158......................... - 5.E-06 - - 1.E+05 - /ET/
Gd-145......................... 9.E-06 7.E-06 - 3.E+05 2.E+05 - ET/ET/
Gd-146......................... 1.E-07 1.E-07 - 4.E+03 4.E+03 - St/St/
Gd-147......................... 7.E-07 6.E-07 - 2.E+04 2.E+04 - ET/ET/
Gd-148......................... 5.E-12 2.E-11 - 2.E-01 9.E-01 - BS/BS/
Gd-149......................... 1.E-06 7.E-07 - 4.E+04 2.E+04 - St/St/
Gd-151......................... 2.E-07 8.E-07 - 9.E+03 3.E+04 - BS/St/
Gd-152......................... 7.E-12 3.E-11 - 2.E-01 1.E+00 - BS/BS/
Gd-153......................... 9.E-08 4.E-07 - 3.E+03 1.E+04 - BS/St/
Gd-159......................... 3.E-06 1.E-06 - 1.E+05 5.E+04 - St/St/
Tb-147......................... - 2.E-06 - - 1.E+05 - /ET/
Tb-149......................... - 1.E-07 - - 6.E+03 - /St/
Tb-150......................... - 2.E-06 - - 8.E+04 - /ET/
Tb-151......................... - 1.E-06 - - 4.E+04 - /ET/
Tb-153......................... - 2.E-06 - - 8.E+04 - /St/
Tb-154......................... - 5.E-07 - - 2.E+04 - /ET/
Tb-155......................... - 2.E-06 - - 8.E+04 - /St/
Tb-156m (24 h)................. - 2.E-06 - - 9.E+04 - /St/
Tb-156m (5 h).................. - 4.E-06 - - 1.E+05 - /St/
Tb-156......................... - 4.E-07 - - 1.E+04 - /E/
Tb-157......................... - 2.E-07 - - 8.E+03 - /BS/
Tb-158......................... - 1.E-08 - - 6.E+02 - /BS/
Tb-160......................... - 1.E-07 - - 3.E+03 - /St/
Tb-161......................... - 4.E-07 - - 1.E+04 - /St/
[[Page 46018]]
Dy-155......................... - 2.E-06 - - 1.E+05 - /ET/
Dy-157......................... - 5.E-06 - - 1.E+05 - /ET/
Dy-159......................... - 2.E-06 - - 8.E+04 - /BS/
Dy-165......................... - 6.E-06 - - 2.E+05 - /ET/
Dy-166......................... - 3.E-07 - - 1.E+04 - /St/
Ho-155......................... - 1.E-05 - - 4.E+05 - /ET/
Ho-157......................... - 2.E-05 - - 1.E+06 - /ET/
Ho-159......................... - 2.E-05 - - 9.E+05 - /ET/
Ho-161......................... - 3.E-05 - - 1.E+06 - /ET/
Ho-162m........................ - 9.E-06 - - 3.E+05 - /ET/
Ho-162......................... - 5.E-05 - - 2.E+06 - /ET/
Ho-164m........................ - 3.E-05 - - 1.E+06 - /St/
Ho-164......................... - 2.E-05 - - 8.E+05 - /ET/
Ho-166m........................ - 7.E-09 - - 2.E+02 - /St/
Ho-166......................... - 6.E-07 - - 2.E+04 - /St/
Ho-167......................... - 4.E-06 - - 1.E+05 - /ET/
Er-161......................... - 3.E-06 - - 1.E+05 - /ET/
Er-165......................... - 2.E-05 - - 1.E+06 - /ET/
Er-169......................... - 6.E-07 - - 2.E+04 - /St/
Er-171......................... - 1.E-06 - - 6.E+04 - /St/
Er-172......................... - 4.E-07 - - 1.E+04 - /St/
Tm-162......................... - 9.E-06 - - 3E+05 - /ET/
Tm-166......................... - 1.E-06 - - 4.E+04 - /ET/
Tm-167......................... - 5.E-07 - - 2.E+04 - /St/
Tm-170......................... - 1.E-07 - - 4.E+03 - /St/
Tm-171......................... - 2.E-07 - - 9.E+03 - /BS/
Tm-172......................... - 4.E-07 - - 1.E+04 - /St/
Tm-173......................... - 2.E-06 - - 8.E+04 - /St/
Tm-175......................... - 8.E-06 - - 2.E+05 - /ET/
Yb-162......................... - 1.E-05 1.E-05 - 5.E+05 5.E+05 /ET/ET
Yb-166......................... - 6.E-07 5.E-07 - 2.E+04 2.E+04 /St/St
Yb-167......................... - 3.E-05 3.E-05 - 1.E+06 1.E+06 /ET/ET
Yb-169......................... - 2.E-07 2.E-07 - 9.E+03 8.E+03 /St/St
Yb-175......................... - 8.E-07 8.E-07 - 3.E+04 2.E+04 /St/St
Yb-177......................... - 6.E-06 5.E-06 - 2.E+05 2.E+05 /ET/ET
Yb-178......................... - 5.E-06 5.E-06 - 1.E+05 1.E+05 /ET/E
Lu-169......................... - 9.E-07 9.E-07 - 3.E+04 3.E+04 /ET/ET
Lu-170......................... - 4.E-07 4.E-07 - 1.E+04 1.E+04 /ET/ET
Lu-171......................... - 6.E-07 6.E-07 - 2.E+04 2.E+04 /St/St
Lu-172......................... - 3.E-07 3.E-07 - 1.E+04 1.E+04 /St/St
Lu-173......................... - 2.E-07 4.E-07 - 8.E+03 1.E+04 /BS/St
Lu-174m........................ - 2.E-07 2.E-07 - 7.E+03 8.E+03 /BS/St
Lu-174......................... - 9.E-08 2.E-07 - 3.E+03 8.E+03 /BS/St
Lu-176m........................ - 3.E-06 3.E-06 - 1.E+05 1.E+05 /St/St
Lu-176......................... - 3.E-09 1.E-08 - 1.E+02 6.E+02 /BS/St
Lu-177m........................ - 5.E-08 4.E-08 - 2.E+03 1.E+03 /St/St
Lu-177......................... - 5.E-07 5.E-07 - 2.E+04 1.E+04 /St/St
Lu-178m........................ - 4.E-06 4.E-06 - 1.E+05 1.E+05 /ET/ET
Lu-178......................... - 8.E-06 8.E-06 - 3.E+05 3.E+05 /ET/ET
Lu-179......................... - 3.E-06 3.E-06 - 1.E+05 1.E+05 /St/St
Hf-170......................... 1.E-06 1.E-06 - 4.E+04 4.E+04 - ET/ET/
Hf-172......................... 6.E-09 3.E-08 - 2.E+02 1.E+03 - BS/BS/
Hf-173......................... 2.E-06 2.E-06 - 9.E+04 8.E+04 - ET/ET/
Hf-175......................... 5.E-07 6.E-07 - 2.E+04 2.E+04 - BS/St/
Hf-177m........................ 2.E-06 1.E-06 - 9.E+04 6.E+04 - ET/ET/
Hf-178m........................ 8.E-10 4.E-09 - 3.E+01 1.E+02 - BS/BS/
Hf-179m........................ 2.E-07 1.E-07 - 8.E+03 6.E+03 - BS/St/
Hf-180m........................ 2.E-06 1.E-06 - 7.E+04 6.E+04 - ET/ET/
Hf-181......................... 1.E-07 1.E-07 - 4.E+03 5.E+03 - BS/St/
Hf-182m........................ 5.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
Hf-182......................... 5.E-10 2.E-09 - 2.E+01 9.E+01 - BS/BS/
Hf-183......................... 6.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
Hf-184......................... 1.E-06 1.E-06 - 5.E+04 4.E+04 - ET/St/
Ta-172......................... - 5.E-06 5.E-06 - 1.E+05 1.E+05 /ET/ET
Ta-173......................... - 3.E-06 3.E-06 - 1.E+05 1.E+05 /E/E
Ta-174......................... - 5.E-06 5.E-06 - 2.E+05 2.E+05 /ET/ET
Ta-175......................... - 1.E-06 1.E-06 - 6.E+04 6.E+04 /ET/ET
Ta-176......................... - 1.E-06 1.E-06 - 3.E+04 3.E+04 /ET/ET
Ta-177......................... - 4.E-06 4.E-06 - 1.E+05 1.E+05 /St/St
Ta-178......................... - 3.E-06 3.E-06 - 1.E+05 1.E+05 /ET/ET
[[Page 46019]]
Ta-179......................... - 4.E-06 1.E-06 - 1.E+05 7.E+04 /St/St
Ta-180m........................ - 9.E-06 9.E-06 - 3.E+05 3.E+05 /St/St
Ta-180......................... - 1.E-07 4.E-08 - 4.E+03 1.E+03 /St/St
Ta-182m........................ - 6.E-06 6.E-06 - 2.E+05 2.E+05 /ET/ET
Ta-182......................... - 9.E-08 7.E-08 - 3.E+03 2.E+03 /St/St
Ta-183......................... - 3.E-07 2.E-07 - 1.E+04 1.E+04 /St/St
Ta-184......................... - 8.E-07 8.E-07 - 3.E+04 3.E+04 /ET/ET
Ta-185......................... - 5.E-06 5.E-06 - 2.E+05 1.E+05 /ET/ET
Ta-186......................... - 7.E-06 7.E-06 - 2.E+05 2.E+05 /ET/ET
W-176.......................... 3.E-06 - - 1.E+05 - - ET/ /
W-177.......................... 5.E-06 - - 2.E+05 - - ET/ /
W-178.......................... 3.E-06 - - 1.E+05 - - ET/ /
W-179.......................... 1.E-04 - - 5.E+06 - - ET/ /
W-181.......................... 1.E-05 - - 4.E+05 - - ET/ /
W-185.......................... 2.E-06 - - 9.E+04 - - St/ /
W-187.......................... 1.E-06 - - 5.E+04 - - ET/ /
W-188.......................... 6.E-07 - - 2.E+04 - - St/ /
Re-177......................... 1.E-05 1.E-05 - 6.E+05 4.E+05 - ET/ET/
Re-178......................... 1.E-05 1.E-05 - 5.E+05 3.E+05 - ET/ET/
Re-181......................... 1.E-06 1.E-06 - 5.E+04 4.E+04 - ;ET/ET/
Re-182 (64 h).................. 4.E-07 3.E-07 - 1.E+04 1.E+04 - ET/St/
Re-182 (12 h).................. 1.E-06 1.E-06 - 4.E+04 4.E+04 - ET/ET/
Re-184m........................ 6.E-07 1.E-07 - 2.E+04 4.E+03 - St/St/
Re-184......................... 7.E-07 3.E-07 - 2.E+04 1.E+04 - ET/St/
Re-186m........................ 4.E-07 7.E-08 - 1.E+04 2.E+03 - St/St/
Re-186......................... 7.E-07 4.E-07 - 2.E+04 1.E+04 - St/St/
Re-187......................... 2.E-04 1.E-04 - 8.E+06 4.E+06 - St/St/
Re-188m........................ 3.E-05 2.E-05 - 1.E+06 1.E+06 - St/St/
Re-188......................... 8.E-07 7.E-07 - 3.E+04 2.E+04 - St/St/
Re-189......................... 1.E-06 9.E-07 - 4.E+04 3.E+04 - St/St/
Os-180......................... 1.E-05 1.E-05 1.E-05 5.E+05 3.E+05 3.E+05 ET/ET/ET
Os-181......................... 3.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Os-182......................... 1.E-06 9.E-07 9.E-07 3.E+04 3.E+04 3.E+04 ET/ET/ET
Os-185......................... 4.E-07 5.E-07 5.E-07 1.E+04 2.E+04 1.E+04 St/St/St
Os-189m........................ 1.E-04 7.E-05 7.E-05 4.E+06 2.E+06 2.E+06 St/St/St
Os-191m........................ 1.E-05 4.E-06 4.E-06 5.E+05 1.E+05 1.E+05 St/St/St
Os-191......................... 1.E-06 4.E-07 3.E-07 5.E+04 1.E+04 1.E+04 St/St/St
Os-193......................... 2.E-06 8.E-07 8.E-07 7.E+04 3.E+04 3.E+04 St/St/St
Os-194......................... 4.E-08 4.E-08 1.E-08 1.E+03 1.E+03 4.E+02 St/St/St
Ir-182......................... 9.E-06 7.E-06 7.E-06 3.E+05 2.E+05 2.E+05 ET/ET/ET
Ir-184......................... 1.E-06 1.E-06 1.E-06 7.E+04 6.E+04 7.E+04 ET/ET/ET
Ir-185......................... 2.E-06 1.E-06 1.E-06 7.E+04 7.E+04 7.E+04 ET/ET/ET
Ir-186 (16 h).................. 8.E-07 7.E-07 7.E-07 2.E+04 2.E+04 2.E+04 ET/ET/ET
Ir-186 (2 h)................... 5.E-06 4.E-06 4.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Ir-187......................... 4.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/ET/ET
Ir-188......................... 6.E-07 6.E-07 6.E-07 2.E+04 2.E+04 2.E+04 ET/ET/ET
Ir-189......................... 3.E-06 1.E-06 1.E-06 1.E+05 5.E+04 4.E+04 St/St/St
Ir-190m (3 h).................. 2.E-06 2.E-06 2.E-06 8.E+04 8.E+04 7.E+04 ET/ET/ET
Ir-190m (1 h).................. 9.E-05 5.E-05 5.E-05 3.E+06 2.E+06 1.E+06 ET/St/St
Ir-190......................... 4.E-07 2.E-07 2.E-07 1.E+04 9.E+03 8.E+03 ET/St/St
Ir-192m........................ 1.E-07 1.E-07 2.E-08 3.E+03 6.E+03 1.E+03 St/St/St
Ir-192......................... 2.E-07 1.E-07 1.E-07 9.E+03 5.E+03 4.E+03 St/St/St
Ir-194m........................ 8.E-08 8.E-08 6.E-08 3.E+03 3.E+03 2.E+03 St/St/St
Ir-194......................... 1.E-06 7.E-07 7.E-07 5.E+04 2.E+04 2.E+04 St/St/St
Ir-195m........................ 2.E-06 2.E-06 2.E-06 9.E+04 7.E+04 7.E+04 ET/ET/ET
Ir-195......................... 7.E-06 5.E-06 4.E-06 2.E+05 1.E+05 1.E+05 ET/ET/ET
Pt-186......................... 3.E-06 - - 1.E+05 - - ET/ /
Pt-188......................... 8.E-07 - - 3.E+04 - - E/ /
Pt-189......................... 3.E-06 - - 1.E+05 - - ET/ /
Pt-191......................... 1.E-06 - - 7.E+04 - - ET/ /
Pt-193m........................ 2.E-06 - - 8.E+04 - - ET/ /
Pt-193......................... 2.E-05 - - 7.E+05 - - ET/ /
Pt-195m........................ 1.E-06 - - 5.E+04 - - ET/ /
Pt-197m........................ 7.E-06 - - 2.E+05 - - ET/ /
Pt-197......................... 3.E-06 - - 1.E+05 - - ET/ /
Pt-199......................... 1.E-05 - - 4.E+05 - - ET/ /
Pt-200......................... 1.E-06 - - 5.E+04 - - St/ /
Au-193......................... 4.E-06 3.E-06 3.E-06 1.E+05 1.E+05 1.E+05 ET/E/St
Au-194......................... 9.E-07 9.E-07 9.E-07 3.E+04 3.E+04 3.E+04 ET/ET/ET
Au-195......................... 3.E-06 7.E-07 4.E-07 1.E+05 2.E+04 1.E+04 ET/St/St
[[Page 46020]]
Au-198m........................ 6.E-07 2.E-07 2.E-07 2.E+04 1.E+04 1.E+04 ET/St/St
Au-198......................... 1.E-06 5.E-07 5.E-07 4.E+04 2.E+04 1.E+04 ET/St/St
Au-199......................... 2.E-06 8.E-07 7.E-07 7.E+04 3.E+04 2.E+04 ET/St/St
Au-200m........................ 5.E-07 4.E-07 4.E-07 1.E+04 1.E+04 1.E+04 ET/ET/ET
Au-200......................... 1.E-05 7.E-06 7.E-06 4.E+05 2.E+05 2.E+05 ET/ET/ET
Au-201......................... 1.E-05 1.E-05 9.E-06 5.E+05 3.E+05 3.E+05 ET/ET/ET
Hg-193m (Org).................. 1.E-06 - - 4.E+04 - - ET/ /
Hg-193m........................ 1.E-06 1.E-06 - 4.E+04 4.E+04 - ET/ET/
Hg-193m (Vapor)................ - 1.E-07 - - 6.E+03 - /St/
Hg-193 (Org)................... 5.E-06 - - 1.E+05 - - ET/ /
Hg-193......................... 5.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
Hg-193 (Vapor)................. - 5.E-07 - - 1.E+04 - /St/
Hg-194 (Org)................... 2.E-08 - - 1.E+03 - - St/ /
Hg-194......................... 3.E-08 1.E-07 - 1.E+03 3.E+03 - St/St/
Hg-194 (Vapor)................. - 1.E-08 - - 5.E+02 - /St/
Hg-195m (Org).................. 1.E-06 - - 5.E+04 - - ET/ /
Hg-195m........................ 1.E-06 8.E-07 - 5.E+04 3.E+04 - ET/St/
Hg-195m (Vapor)................ - 6.E-08 - - 2.E+03 - /St/
Hg-195 (Org)................... 6.E-06 - - 2.E+05 - - ET/ /
Hg-195......................... 6.E-06 6.E-06 - 2.E+05 2.E+05 - ET/ET/
Hg-195 (Vapor)................. - 4.E-07 - - 1.E+04 - /St/
Hg-197m (Org).................. 1.E-06 - - 5.E+04 - - ET/ /
Hg-197m........................ 1.E-06 8.E-07 - 5.E+04 3.E+04 - ET/St/
Hg-197m (Vapor)................ - 9.E-08 - - 3.E+03 - /St/
Hg-197 (Org)................... 4.E-06 - - 1.E+05 - - ET/ /
Hg-197......................... 4.E-06 2.E-06 - 1.E+05 7.E+04 - ET/St/
Hg-197 (Vapor)................. - 1.E-07 - - 4.E+03 - /St/
Hg-199m (Org).................. 8.E-06 - - 3.E+05 - - ET/ /
Hg-199m........................ 8.E-06 5.E-06 - 3.E+05 1.E+05 - ET/ET/
Hg-199m (Vapor)................ - 3.E-06 - - 1.E+05 - /St/
Hg-203 (Org)................... 7.E-07 - - 2.E+04 - - St/ /
Hg-203......................... 9.E-07 2.E-07 - 3.E+04 1.E+04 - St/St/
Hg-203 (Vapor)................. - 8.E-08 - - 2.E+03 - /St/
Tl-194m........................ 5.E-06 - - 2.E+05 - - ET/ /
Tl-194......................... 2.E-05 - - 8.E+05 - - ET/ /
Tl-195......................... 6.E-06 - - 2.E+05 - - ET/ /
Tl-197......................... 8.E-06 - - 2.E+05 - - ET/ /
Tl-198m........................ 2.E-06 - - 9.E+04 - - ET/ /
Tl-198......................... 1.E-06 - - 5.E+04 - - ET/ /
Tl-199......................... 5.E-06 - - 2.E+05 - - ET/ /
Tl-200......................... 8.E-07 - - 3.E+04 - - ET/ /
Tl-201......................... 4.E-06 - - 1.E+05 - - ET/ /
Tl-202......................... 1.E-06 - - 5.E+04 - - ET/ /
Tl-204......................... 9.E-07 - - 3.E+04 - - St/ /
Pb-195m........................ 7.E-06 - - 2.E+05 - - ET/ /
Pb-198......................... 2.E-06 - - 9.E+04 - - ET/ /
Pb-199......................... 4.E-06 - - 1.E+05 - - ET/ /
Pb-200......................... 1.E-06 - - 4.E+04 - - ET/ /
Pb-201......................... 2.E-06 - - 7.E+04 - - ET/ /
Pb-202m........................ 1.E-06 - - 6.E+04 - - ET/ /
Pb-202......................... 4.E-08 - - 1.E+03 - - St/ /
Pb-203......................... 2.E-06 - - 7.E+04 - - ET/ /
Pb-205......................... 9.E-07 - - 3.E+04 - - BS/ /
Pb-209......................... 9.E-06 - - 3.E+05 - - ET/ /
Pb-210......................... 1.E-10 - - 5.E+00 - - BS/ /
Pb-211......................... 4.E-08 - - 1.E+03 - - ET/ /
Pb-212......................... 5.E-09 - - 2.E+02 - - ET/ /
Pb-214......................... 4.E-08 - - 1.E+03 - - ET/ /
Bi-200......................... 5.E-06 4.E-06 - 2.E+05 1.E+05 - ET/ET/
Bi-201......................... 3.E-06 2.E-06 - 1.E+05 1.E+05 - ET/ET/
Bi-202......................... 2.E-06 2.E-06 - 9.E+04 9.E+04 - ET/ET/
Bi-203......................... 7.E-07 7.E-07 - 2.E+04 2.E+04 - ET/ET/
Bi-205......................... 4.E-07 4.E-07 - 1.E+04 1.E+04 - ET/ET/
Bi-206......................... 2.E-07 2.E-07 - 9.E+03 8.E+03 - ET/ET/
Bi-207......................... 4.E-07 1.E-07 - 1.E+04 6.E+03 - ET/St/
Bi-210m........................ 3.E-09 2.E-10 - 1.E+02 9.E+00 - K/St/
Bi-210......................... 1.E-07 9.E-09 - 6.E+03 3.E+02 - K/St/
Bi-212......................... 1.E-08 8.E-09 - 4.E+02 3.E+02 - ET/ET/
Bi-213......................... 1.E-08 7.E-09 - 4.E+02 2.E+02 - ET/ET/
Bi-214......................... 1.E-08 1.E-08 - 6.E+02 4.E+02 - ET/ET/
[[Page 46021]]
Po-203......................... 5.E-06 4.E-06 - 1.E+05 1.E+05 - ET/ET/
Po-205......................... 4.E-06 3.E-06 - 1.E+05 1.E+05 - ET/ET/
Po-207......................... 1.E-06 1.E-06 - 7.E+04 6.E+04 - ET/ET/
Po-210......................... 7.E-10 2.E-10 - 2.E+01 9.E+00 - K/St/
At-207......................... 1.E-06 2.E-07 - 4.E+04 1.E+04 - St/St/
At-211......................... 7.E-09 5.E-09 - 2.E+02 1.E+02 - ET/St/
Rn-220 \5\..................... 1.E-08 - - 6.E+02 - - -
Rn-222 \5\..................... 8.E-08 - - 3.E+03 - - -
Fr-222......................... 1.E-08 - - 3.E+02 - - ET/ /
Fr-223......................... 4.E-07 - - 1.E+04 - - St/ /
Ra-223......................... - 9.E-11 - - 3.E+00 - /St/
Ra-224......................... - 2.E-10 - - 8.E+00 - /St/
Ra-225......................... - 1.E-10 - - 4.E+00 - /St/
Ra-226......................... - 2.E-10 - - 9.E+00 - /St/
Ra-227......................... - 8.E-07 - - 3.E+04 - /BS/
Ra-228......................... - 1.E-10 - - 5.E+00 - /BS/
Ac-224......................... 1.E-08 6.E-09 5.E-09 6.E+02 2.E+02 2.E+02 BS/St/St
Ac-225......................... 2.E-10 9.E-11 8.E-11 7.E+00 3.E+00 3.E+00 BS/St/St
Ac-226......................... 1.E-09 6.E-10 5.E-10 4.E+01 2.E+01 2.E+01 ET/St/St
Ac-227......................... 2.E-13 1.E-12 1.E-11 1.E-02 5.E-02 4.E-01 BS/BS/St
Ac-228......................... 6.E-09 3.E-08 4.E-08 2.E+02 1.E+03 1.E+03 BS/BS/St
Th-226......................... - 4.E-09 4.E-09 - 1.E+02 1.E+02 /ET/ET
Th-227......................... - 9.E-11 7.E-11 - 3.E+00 2.E+00 /St/St
Th-228......................... - 2.E-11 2.E-11 - 7.E-01 8.E-01 /BS/St
Th-229......................... - 2.E-12 1.E-11 - 7.E-02 4.E-01 /BS/St
Th-230......................... - 3.E-12 4.E-11 - 1.E-01 1.E+00 /BS/BS
Th-231......................... - 1.E-06 1.E-06 - 5.E+04 5.E+04 /St/St
Th-232......................... - 3.E-12 4.E-11 - 1.E-01 1.E+00 /BS/BS
Th-234......................... - 1.E-07 9.E-08 - 3.E+03 3.E+03 /St/St
Pa-227......................... - 4.E-09 4.E-09 - 1.E+02 1.E+02 /ET/ET
Pa-228......................... - 1.E-08 1.E-08 - 3.E+02 4.E+02 /BS/St
Pa-230......................... - 1.E-09 9.E-10 - 4.E+01 3.E+01 /St/St
Pa-231......................... - 1.E-12 1.E-11 - 4.E-02 4.E-01 /BS/BS
Pa-232......................... - 1.E-08 1.E-07 - 6.E+02 7.E+03 /BS/BS
Pa-233......................... - 2.E-07 1.E-07 - 7.E+03 6.E+03 /St/St
Pa-234......................... - 7.E-07 7.E-07 - 2.E+04 2.E+04 /ET/ET
U-230.......................... 6.E-10 5.E-11 4.E-11 2.E+01 2.E+00 1.E+00 K/St/St
U-231.......................... 2.E-06 1.E-06 1.E-06 8.E+04 4.E+04 4.E+04 ET/St/St
U-232.......................... 5.E-11 1.E-10 2.E-11 2.E+00 4.E+00 7.E-01 BS/St/ET
U-233.......................... 4.E-10 2.E-10 7.E-11 1.E+01 9.E+00 2.E+00 BS/St/ET
U-234.......................... 5.E-10 2.E-10 7.E-11 1.E+01 9.E+00 2.E+00 BS/St/ET
U-235.......................... 5.E-10 3.E-10 8.E-11 1.E+01 1.E+01 3.E+00 BS/St/ET
U-236.......................... 5.E-10 2.E-10 7.E-11 1.E+01 1.E+01 2.E+00 BS/St/ET
U-237.......................... 1.E-06 3.E-07 3.E-07 4.E+04 1.E+04 1.E+04 ET/St/St
U-238.......................... 5.E-10 3.E-10 8.E-11 2.E+01 1.E+01 3.E+00 BS/St/ET
U-239.......................... 1.E-05 9.E-06 9.E-06 5.E+05 3.E+05 3.E+05 ET/ET/ET
U-240.......................... 1.E-06 7.E-07 6.E-07 5.E+04 2.E+04 2.E+04 ET/St/St
Np-232......................... - 3.E-06 - - 1.E+05 - /BS/
Np-233......................... - 7.E-05 - - 2.E+06 - /ET/
Np-234......................... - 5.E-07 - - 2.E+04 - /ET/
Np-235......................... - 1.E-06 - - 4.E+04 - /BS/
Np-236 (1.E+05 yr)............. - 4.E-11 - - 1.E+00 - /BS/
Np-236 (22 h).................. - 5.E-08 - - 1.E+03 - /BS/
Np-237......................... - 8.E-12 - - 3.E-01 - /BS/
Np-238......................... - 1.E-07 - - 4.E+03 - /BS/
Np-239......................... - 5.E-07 - - 1.E+04 - /St/
Np-240......................... - 2.E-06 - - 8.E+04 - /ET/
Pu-234......................... - 3.E-08 3.E-08 - 1.E+03 1.E+03 /St/St
Pu-235......................... - 9.E-05 8.E-05 - 3.E+06 3.E+06 /ET/ET
Pu-236......................... - 1.E-11 7.E-11 - 6.E-01 2.E+00 /BS/St
Pu-237......................... - 1.E-06 1.E-06 - 7.E+04 6.E+04 /St/St
Pu-238......................... - 6.E-12 5.E-11 - 2.E-01 1.E+00 /BS/St
Pu-239......................... - 5.E-12 6.E-11 - 2.E-01 2.E+00 /BS/BS
Pu-240......................... - 5.E-12 6.E-11 - 2.E-01 2.E+00 /BS/BS
Pu-241......................... - 2.E-10 2.E-09 - 1.E+01 1.E+02 /BS/BS
Pu-242......................... - 5.E-12 6.E-11 - 2.E-01 2.E+00 /BS/BS
Pu-243......................... - 5.E-06 5.E-06 - 1.E+05 1.E+05 /E/E
Pu-244......................... - 5.E-12 6.E-11 - 2.E-01 2.E+00 /BS/BS
Pu-245......................... - 9.E-07 8.E-07 - 3.E+04 3.E+04 /St/St
Pu-246......................... - 8.E-08 8.E-08 - 3.E+03 2.E+03 /St/St
[[Page 46022]]
Am-237......................... - 8.E-06 - - 3.E+05 - /ET/
Am-238......................... - 2.E-06 - - 9.E+04 - /BS/
Am-239......................... - 1.E-06 - - 6.E+04 - /ET/
Am-240......................... - 7.E-07 - - 2.E+04 - /ET/
Am-241......................... - 5.E-12 - - 1.E-01 - /BS/
Am-242m........................ - 5.E-12 - - 1.E-01 - /BS/
Am-242......................... - 4.E-08 - - 1.E+03 - /St/
Am-243......................... - 5.E-12 - - 1.E-01 - /BS/
Am-244m........................ - 3.E-06 - - 1.E+05 - /BS/
Am-244......................... - 1.E-07 - - 5.E+03 - /BS/
Am-245......................... - 5.E-06 - - 2.E+05 - /ET/
Am-246m........................ - 6.E-06 - - 2.E+05 - /ET/
Am-246......................... - 2.E-06 - - 9.E+04 - /ET/
Cm-238......................... - 1.E-07 - - 4.E+03 - /St/
Cm-240......................... - 3.E-10 - - 7.E+01 - /St/
Cm-241......................... - 2.E-08 - - 8.E+02 - /St/
Cm-242......................... - 1.E-10 - - 5.E+00 - /St/
Cm-243......................... - 7.E-12 - - 2.E-01 - /BS/
Cm-244......................... - 9.E-12 - - 3.E-01 - /BS/
Cm-245......................... - 5.E-12 - - 1.E-01 - /BS/
Cm-246......................... - 5.E-12 - - 1.E-01 - /BS/
Cm-247......................... - 5.E-12 - - 2.E-01 - /BS/
Cm-248......................... - 1.E-12 - - 5.E-02 - /BS/
Cm-249......................... - 8.E-06 - - 3.E+05 - /ET/
Cm-250......................... - 2.E-13 - - 8.E-03 - /BS/
Bk-245......................... - 3.E-07 - - 1.E+04 - /St/
Bk-246......................... - 8.E-07 - - 3.E+04 - /ET/
Bk-247......................... - 3.E-12 - - 1.E-01 - /BS/
Bk-249......................... - 1.E-09 - - 5.E+01 - /BS/
Bk-250......................... - 2.E-07 - - 9.E+03 - /BS/
Cf-244......................... - 1.E-08 - - 5.E+02 - /ET/
Cf-246......................... - 1.E-09 - - 5.E+01 - /St/
Cf-248......................... - 5.E-11 - - 2.E+00 - /BS/
Cf-249......................... - 3.E-12 - - 1.E-01 - /BS/
Cf-250......................... - 7.E-12 - - 2.E-01 - /BS/
Cf-251......................... - 3.E-12 - - 1.E-01 - /BS/
Cf-252......................... - 1.E-11 - - 6.E-01 - /BS/
Cf-253......................... - 5.E-10 - - 2.E+01 - /St/
Cf-254......................... - 2.E-11 - - 8.E-01 - /BS/
Es-250......................... - 4.E-07 - - 1.E+04 - /BS/
Es-251......................... - 3.E-07 - - 1.E+04 - /St/
Es-253......................... - 2.E-10 - - 9.E+00 - /St/
Es-254m........................ - 1.E-09 - - 5.E+01 - /St/
Es-254......................... - 6.E-11 - - 2.E+00 - /BS/
Fm-252......................... - 2.E-09 - - 8.E+01 - /St/
Fm-253......................... - 1.E-09 - - 6.E+01 - /St/
Fm-254......................... - 6.E-09 - - 2.E+02 - /ET/
Fm-255......................... - 2.E-09 - - 8.E+01 - /St/
Fm-257......................... - 1.E-10 - - 4.E+00 - /St/
Md-257......................... - 2.E-08 - - 1.E+03 - /St/
Md-258......................... - 1.E-10 - - 4.E+00 - /St/
--------------------------------------------------------------------------------------------------------------------------------------------------------
For any single radionuclide not listed above with decay mode
other than alpha emission or spontaneous fission and with
radioactive half-life greater than two hours, the DAC value shall be
4.E-11 [mu]Ci/ml (1 Bq/m3).
For any single radionuclide not listed above that decays by
alpha emission or spontaneous fission, or any mixture for which the
identity or the concentration of any radionuclide in the mixture is
not known, the DAC value shall be 2.E-13 [mu]Ci/ml (8.E-03 Bq/m3).
Footnotes for Appendix A
1 A determination of whether the DACs are controlled
by stochastic (St) or nonstochastic (organ) dose, or if they both
give the same result (E), for each lung retention class, is given in
this column. The key to the organ notation for nonstochastic dose
is: BS = Bone surface, ET = Extrathoracic, K = Kidney, L = Liver,
and T = Thyroid. A blank indicates that no calculations were
performed for the material type shown.
2 The ICRP identifies these materials as soluble or
reactive gases and vapors or highly soluble or reactive gases and
vapors. For tritiated water, the inhalation DAC values allow for an
additional 50% absorption through the skin, as described in ICRP
Publication No. 68, Dose Coefficients for Intakes of Radionuclides
by Workers. For elemental tritium, the DAC values include a factor
that irradiation from gas within the lungs might increase the dose by 20%.
3 A dash indicates no values given for this data category.
4 DAC values derived using hafnium tritide particle
and are based on observed activity (i.e, only radiation emitted from
the particle is considered). DAC values derived using methodology
found in Radiological Control Programs for Special Tritium
Compounds, DOE-HDBK-1184-2004.
[[Page 46023]]
5 These values are appropriate for protection from
radon combined with its short-lived daughters and are based on
information given in ICRP Publication 65: Protection Against Radon-
222 at Home and at Work and in DOE-STD-1121-98: Internal Dosimetry.
The values given are for 100% equilibrium concentration conditions
of the radon daughters with the parent. To allow for an actual
measured equilibrium concentration or a demonstrated equilibrium
concentration, the values given in this table should be multiplied
by the ratio (100%/actual %) or (100%/demonstrated %), respectively.
Alternatively, the DAC values for Rn-220 and Rn-222 may be replaced
by 2.5 WL* and 0.83 WL*, respectively, for appropriate limiting of
daughter concentrations.
* A ``Working Level'' (WL) is any combination of short-lived
radon daughters, in one liter of air without regard to the degree of
equilibrium, that will result in the ultimate emission of 1.3 E+05
MeV of alpha energy.
30. Appendix C to part 835 is revised to read as follows:
Appendix C to Part 835--Derived Air Concentration (DAC) for Workers
From External Exposure During Immersion in a Cloud of Airborne
Radioactive Material
a. The data presented in appendix C are to be used for
controlling occupational exposures in accordance with Sec. 835.209,
identifying the need for air monitoring in accordance with Sec.
835.403 and identifying the need for posting of airborne
radioactivity areas in accordance with Sec. 835.603(d).
b. The air immersion DAC values shown in this appendix are based
on a stochastic dose limit of 5 rems (0.05 Sv) per year. Four
columns of information are presented: (1) radionuclide; (2) half-
life in units of seconds (s), minutes (min), hours (h), days (d), or
years (yr); (3) air immersion DAC in units of [mu]Ci/ml; and (4) air
immersion DAC in units of Bq/m3. The data are listed by
radionuclide in order of increasing atomic mass. The air immersion
DACs were calculated for a continuous, nonshielded exposure via
immersion in a semi-infinite cloud of airborne radioactive material.
The DACs listed in this appendix may be modified to allow for
submersion in a cloud of finite dimensions.
c. The DAC values are given for individual radionuclides. For
known mixtures of radionuclides, determine the sum of the ratio of
the observed concentration of a particular radionuclide and its
corresponding DAC for all radionuclides in the mixture. If this sum
exceeds unity (1), then the DAC has been exceeded. For unknown
radionuclides, the most restrictive DAC (lowest value) for those
isotopes not known to be absent shall be used.
----------------------------------------------------------------------------------------------------------------
Air Immersion DASC
-----------------------------------------------------------------------------------------------------------------
Radionuclide Half-Life ([mu]Ci/ml) (Bq/m3
----------------------------------------------------------------------------------------------------------------
Ar-37................................. 35.02 d.................. 1.E+00 4.E+10
Ar-39................................. 269 yr................... 4.E-04 1.E+07
Ar-41................................. 1.827 h.................. 1.E-06 3.E+04
Kr-74................................. 11.5 min................. 1.E-06 4.E+04
Kr-76................................. 14.8 h................... 3.E-06 1.E+05
Kr-77................................. 74.7 h................... 1.E-06 5.E+04
Kr-79................................. 35.04 h.................. 5.E-06 2.E+05
Kr-81................................. 2.1E+05 yr............... 2.E-04 9.E+06
Kr-83m................................ 1.83 h................... 2.E-02 9.E+08
Kr-85................................. 10.72 yr................. 2.E-04 9.E+06
Kr-85m................................ 4.48 h................... 9.E-06 3.E+05
Kr-87................................. 76.3 min................. 1.E-06 5.E+04
Kr-88................................. 2.84 h................... 6.E-07 2.E+04
Xe-120................................ 40.0 min................. 3.E-06 1.E+05
Xe-121................................ 40.1 min................. 7.E-07 2.E+04
Xe-122................................ 20.1 h................... 2.E-05 1.E+06
Xe-123................................ 2.14 h................... 2.E-06 8.E+04
Xe-125................................ 16.8 h................... 5.E-06 2.E+05
Xe-127................................ 36.406 d................. 5.E-06 2.E+05
Xe-129m............................... 8.89 d................... 6.E-05 2.E+06
Xe-131m............................... 11.84 d.................. 1.E-04 6.E+06
Xe-133................................ 5.245 d.................. 4.E-05 1.E+06
Xe-133m............................... 2.19 d................... 4.E-05 1.E+06
Xe-135................................ 9.11 h................... 5.E-06 2.E+05
Xe-135m............................... 15.36 min................ 3.E-06 1.E+05
Xe-138................................ 14.13 min................ 1.E-06 4.E+04
----------------------------------------------------------------------------------------------------------------
For any single radionuclide not listed above with decay mode
other than alpha emission or spontaneous fission and with
radioactive half-life less than two hours, the DAC value shall be
6.E-06 [mu]Ci/ml (2.E+04 Bq/m3).
31. Appendix D to part 835 is revised to read as follows:
Appendix D to Part 835--Surface Contamination Values
The data presented in appendix D are to be used in identifying
and posting contamination and high contamination areas in accordance
with Sec. 835.603(e) and (f) and identifying the need for surface
contamination monitoring and control in accordance with Sec.
835.1101 and 1102.
Surface Contamination Values\1\ in dpm/100 cm\2\
------------------------------------------------------------------------
Total (fixed +
Radionuclide Removable 2 4 removable) 2 3
------------------------------------------------------------------------
U-nat, U-235, U-238, and associated \7\ 1,000 \7\ 5,000
decay products......................... products
Transuranics, Ra-226, Ra-228, Th-230, Th- 20 500
228, Pa-231, Ac-227, I-125, I-129......
[[Page 46024]]
Th-nat, Th-232, Sr-90 (including mixed 200 1,000
fission products where the Sr-90
fraction is 90 percent or more of the
total activity), Ra-223, Ra-224, U-232,
I-126, I-131, I-133....................
Mixed fission products where the Sr-90 600 3,000
fraction is more than 50 percent but
less than 90 percent of the total
activity...............................
Beta-gamma emitters (nuclides with decay 1,000 5,000
modes other than alpha emission or
spontaneous fission) except Sr-90 and
others noted above \5\.................
Tritium and tritiated compounds \6\..... 10,000 N/A
------------------------------------------------------------------------
\1\ The values in this appendix, with the exception noted in footnote 6
below, apply to radioactive contamination deposited on, but not
incorporated into the interior or matrix of, the contaminated item.
Where surface contamination by both alpha- and beta-gamma-emitting
nuclides exists, the limits established for alpha- and beta-gamma-
emitting nuclides apply independently.
\2\ As used in this table, dpm (disintegrations per minute) means the
rate of emission by radioactive material as determined by correcting
the counts per minute observed by an appropriate detector for
background, efficiency, and geometric factors associated with the
instrumentation.
\3\ The levels may be averaged over one square meter provided the
maximum surface activity in any area of 100 cm\2\ is less than three
times the value specified. For purposes of averaging, any square meter
of surface shall be considered to be above the surface contamination
value if: (1) From measurements of a representative number of sections
it is determined that the average contamination level exceeds the
applicable value; or (2) it is determined that the sum of the activity
of all isolated spots or particles in any 100 cm\2\ area exceeds three
times the applicable value.
\4\ The amount of removable radioactive material per 100 cm\2\ of
surface area should be determined by swiping the area with dry filter
or soft absorbent paper, applying moderate pressure, and then
assessing the amount of radioactive material on the swipe with an
appropriate instrument of known efficiency. (Note--The use of dry
material may not be appropriate for tritium.) When removable
contamination on objects of surface area less than 100 cm\2\ is
determined, the activity per unit area shall be based on the actual
area and the entire surface shall be wiped. It is not necessary to use
swiping techniques to measure removable contamination levels if direct
scan surveys indicate that the total residual surface contamination
levels are within the limits for removable contamination.
\5\ This category of radionuclides includes mixed fission products where
the Sr-90 fraction is 50 percent or less of the total activity.
\6\ Tritium contamination may diffuse into the volume or matrix of
materials. Evaluation of surface contamination shall consider the
extent to which such contamination may migrate to the surface in order
to ensure the surface contamination value provided in this appendix is
not exceeded. Once this contamination migrates to the surface, it may
be removable, not fixed; therefore, a ``Total'' value does not apply.
\7\ These limits only apply to the alpha emitters within the respective
decay series.
32. Appendix E to part 835 is revised to read as follows:
Appendix E to Part 835--Values for Establishing Sealed Radioactive
Source Accountability and Radioactive Material Posting and Labeling
Requirements
The data presented in appendix E are to be used for identifying
accountable sealed radioactive sources and radioactive material
areas as those terms are defined at Sec. 835.2(a), establishing the
need for radioactive material area posting in accordance with Sec.
835.603(g), and establishing the need for radioactive material
labeling in accordance with Sec. 835.605.
------------------------------------------------------------------------
Nuclide Activity ([mu]Ci)
------------------------------------------------------------------------
H-3........................................ 1.5E+08
Be-7....................................... 3.1E+03
Be-10...................................... 1.4E+05
C-14....................................... 4.6E+06
Na-22...................................... 1.9E+01
Al-26...................................... 1.5E+01
Si-32...................................... 4.9E+04
S-35....................................... 2.4E+06
Cl-36...................................... 5.2E+05
K-40....................................... 2.7E+02
Ca-41...................................... 9.3E+06
Ti-44...................................... 1.5E+02
Ca-45...................................... 1.1E+06
Sc-46...................................... 6.2E+01
V-49....................................... 1.0E+08
Mn-53...................................... 7.5E+07
Mn-54...................................... 6.5E+01
Fe-55...................................... 2.9E+06
Fe-59...................................... 1.9E+02
Fe-60...................................... 8.1E+03
Co-56...................................... 3.9E+01
Co-57...................................... 2.3E+02
Co-58...................................... 1.3E+02
Co-60...................................... 1.7E+01
Ni-59...................................... 3.2E+06
Ni-63...................................... 1.3E+06
Zn-65...................................... 1.1E+02
Ge-68...................................... 5.6E+02
As-73...................................... 5.3E+02
Se-75...................................... 6.3E+01
Se-79...................................... 8.7E+05
Rb-83...................................... 9.1E+01
Rb-84...................................... 2.0E+02
Sr-85...................................... 1.2E+02
Sr-89...................................... 4.8E+05
Sr-90...................................... 3.5E+04
Y-88....................................... 3.3E+01
Y-91....................................... 5.0E+04
Zr-88...................................... 1.1E+02
Zr-93...................................... 9.3E+04
Zr-95...................................... 1.9E+02
Nb-91...................................... 6.9E+01
Nb-91m..................................... 3.6E+02
Nb-92...................................... 1.8E+01
Nb-93m..................................... 4.4E+02
Nb-94...................................... 2.3E+01
Nb-95...................................... 3.4E+02
Mo-93...................................... 7.7E+01
Tc-95m..................................... 1.3E+02
Tc-97...................................... 8.1E+01
Tc-97m..................................... 3.5E+02
Tc-98...................................... 2.5E+01
Tc-99...................................... 8.4E+05
Rh-101..................................... 8.7E+05
Rh-102..................................... 3.0E+05
Rh-102m.................................... 6.4E+05
Ru-103..................................... 4.4E+02
Ru-106..................................... 2.5E+02
Ag-105..................................... 3.3E+06
Ag-108m.................................... 1.8E+01
Ag-110m.................................... 2.2E+01
Pd-107..................................... 9.3E+06
Cd-109..................................... 1.6E+02
Cd-113m.................................... 2.0E+04
Cd-115m.................................... 1.0E+04
Sn-113..................................... 3.1E+02
Sn-119m.................................... 3.3E+02
Sn-121m.................................... 8.1E+05
Sn-123..................................... 1.3E+04
Sn-126..................................... 1.8E+02
In-114m.................................... 7.7E+02
Te-121m.................................... 1.8E+02
Te-123m.................................... 2.8E+02
Te-125m.................................... 4.4E+02
Te-127m.................................... 8.0E+02
Te-129m.................................... 2.3E+03
Sb-124..................................... 9.1E+01
Sb-125..................................... 6.7E+01
I-125...................................... 3.5E+02
I-129...................................... 1.8E+02
Ba-133..................................... 5.1E+01
Cs-134..................................... 2.6E+01
Cs-135..................................... 1.3E+06
Cs-137..................................... 6.0E+01
La-137..................................... 2.7E+05
Ce-139..................................... 2.4E+02
Ce-141..................................... 2.4E+03
Ce-144..................................... 1.4E+03
Pm-143..................................... 1.3E+02
Pm-144..................................... 2.9E+01
Pm-145..................................... 2.6E+02
Pm-146..................................... 4.4E+01
Pm-147..................................... 7.7E+05
Pm-148m.................................... 1.0E+02
Sm-145..................................... 2.4E+06
Sm-146..................................... 4.0E+02
Sm-151..................................... 2.5E+05
Gd-146..................................... 5.1E+05
[[Page 46025]]
Gd-148..................................... 9.0E+01
Gd-151..................................... 2.9E+06
Gd-153..................................... 2.1E+02
Eu-148..................................... 1.1E+06
Eu-149..................................... 1.1E+07
Eu-152..................................... 3.1E+01
Eu-154..................................... 3.1E+01
Eu-155..................................... 3.6E+02
Tb-157..................................... 2.5E+03
Tb-158..................................... 9.0E+04
Tb-160..................................... 1.2E+02
Dy-159..................................... 1.0E+07
Ho-166m.................................... 2.1E+01
Yb-169..................................... 5.5E+02
Tm-170..................................... 8.4E+03
Tm-171..................................... 2.8E+04
Hf-172..................................... 7.3E+04
Hf-175..................................... 3.0E+06
Hf-178m.................................... 8.7E+03
Hf-181..................................... 3.4E+02
Hf-182..................................... 7.5E+03
Lu-173..................................... 1.8E+06
Lu-174..................................... 9.3E+05
Lu-174m.................................... 1.0E+06
Lu-177m.................................... 5.8E+01
Ta-179..................................... 9.3E+06
Ta-182..................................... 7.3E+01
W-181...................................... 1.0E+03
W-185...................................... 3.9E+06
W-188...................................... 6.3E+04
Re-183..................................... 5.3E+02
Re-184..................................... 2.6E+02
Re-184m.................................... 1.5E+02
Re-186m.................................... 3.4E+05
Os-185..................................... 1.3E+02
Os-194..................................... 6.4E+04
Ir-192..................................... 1.3E+02
Ir-192m.................................... 1.4E+05
Ir-194m.................................... 2.7E+01
Pt-193..................................... 8.7E+07
Hg-194..................................... 5.2E+04
Hg-203..................................... 4.9E+02
Au-195..................................... 4.8E+02
Pb-202..................................... 1.9E+05
Pb-205..................................... 9.0E+01
Pb-210..................................... 9.2E+01
Tl-204..................................... 2.2E+04
Bi-207..................................... 1.7E+01
Bi-208..................................... 1.5E+01
Bi-210m.................................... 1.2E+03
Po-209..................................... 6.3E+03
Po-210..................................... 1.2E+03
Ra-226..................................... 2.2E+02
Ra-228..................................... 1.5E+03
Ac-227..................................... 4.2E+00
Th-228..................................... 8.4E+01
Th-229..................................... 3.1E+01
Th-230..................................... 5.4E+00
Th-232..................................... 9.3E+01
Pa-231..................................... 3.0E+01
U-232...................................... 1.0E+02
U-233...................................... 3.9E+02
U-234...................................... 2.9E+02
U-235...................................... 6.7E+01
U-236...................................... 3.1E+02
U-238...................................... 3.5E+02
Np-235..................................... 1.1E+02
Np-236..................................... 2.1E+01
Np-237..................................... 4.9E+01
Pu-236..................................... 2.0E+02
Pu-237..................................... 3.3E+02
Pu-238..................................... 9.0E+01
Pu-239..................................... 8.4E+01
Pu-240..................................... 8.4E+01
Pu-241..................................... 4.6E+03
Pu-242..................................... 8.7E+01
Pu-244..................................... 9.0E+01
Am-241..................................... 7.2E+01
Am-242m.................................... 1.1E+02
Am-243..................................... 7.3E+01
Cm-241..................................... 1.0E+05
Cm-242..................................... 6.2E+02
Cm-243..................................... 4.8E+01
Cm-244..................................... 1.5E+02
Cm-245..................................... 5.0E+01
Cm-246..................................... 1.0E+02
Cm-247..................................... 8.5E+01
Cm-248..................................... 2.8E+01
Cm-250..................................... 5.4E+00
Bk-247..................................... 6.0E+01
Bk-249..................................... 2.7E+04
Cf-248..................................... 4.4E+02
Cf-249..................................... 5.5E+01
Cf-250..................................... 1.2E+02
Cf-251..................................... 5.3E+01
Cf-252..................................... 5.2E+00
Cf-254..................................... 1.2E+02
Es-254..................................... 6.3E+01
Es-255..................................... 8.8E+03
Fm-257..................................... 5.1E+02
Md-258..................................... 6.1E+02
------------------------------------------------------------------------
Any alpha emitting radionuclide not listed above and mixtures of
alpha emitters of unknown composition have a value of 10 [mu]Ci.
Except as discussed below, any radionuclide other than alpha
emitting radionuclides not listed above and mixtures of beta
emitters of unknown composition have a value of 100 [mu]Ci.
Any type of tritiated particulate or organically-bound tritiated
compound has a value of 10 Ci.
Note: Where there is involved a combination of radionuclides in
known amounts, derive the value for the combination as follows:
determine, for each radionuclide in the combination, the ratio
between the quantity present in the combination and the value
otherwise established for the specific radionuclide when not in
combination. If the sum of such ratios for all radionuclides in the
combination exceeds unity (1), then the accountability criterion has
been exceeded.
[FR Doc. 06-6579 Filed 8-9-06; 8:45 am]
BILLING CODE 6450-01-P