doc_fn:    oldord/5480/o548011.html
DocType:  ArcOld
ID:        DOE O 5480.11
Title:     Radiation Protection for Occupational Workers
Summary:   
Org:
Date_Issue: 12/21/1988
Date_Close: 09/29/1995
VdkVgwKey: oldord-9
Directive: 5480.11
Text:


U.S. Department of Energy                                   ORDER
     Washington, D.C.                                    DOE 5480.11
                                                           12-21-88
                                                    Chg 3:  6-17-92

SUBJECT:  RADIATION PROTECTION FOR OCCUPATIONAL WORKERS

1.  PURPOSE.  To establish radiation protection standards and program
    requirements for the Department of Energy (DOE) and DOE contractor
    operations with respect to the protection of the worker from ionizing
    radiation.

2.  SCOPE.  The provisions of this Order apply to all Departmental Elements
    and contractors performing work for the Department as provided by law
    and/or contract and as implemented by the appropriate contracting
    officer.

3.  SUPERCESSION.  This Order supercedes DOE 5480.1A, ENVIRONMENTAL
    PROTECTION, SAFETY AND HEALTH PROTECTION PROGRAM FOR DOE OPERATIONS, of
    8-13-81, Chapter XI, "Requirements for Radiation Protection," except
    areas pertaining to radiation protection standards for the public and
    the environment.

4.  EFFECTIVE DATE.  1-1-89.

5.  POLICY.

    a.  It is the policy of DOE to implement radiation protection standards
        that are consistent with the Presidential approved guidance to
        Federal Agencies promulgated by the Environmental Protection Agency
        (EPA) and based on the recommendations by authoritative
        organizations, e.g., the National Council on Radiation Protection
        and Measurements (NCRP), and the International Commission on
        Radiological Protection (ICRP).

    b.  It is the policy of DOE to operate its facilities and conduct its
        activities so that radiation exposures are maintained within the
        limits promulgated by this Order and as far below the limits of this
        Order as reasonably achievable.  This policy applies to annual,
        committed, and cumulative dose equivalents.

    c.  It is the policy of DOE that a Radiological Control Program be
        established that implements by 12-1-92 the provisions set forth in
        the DOE Radiological Control (RadCon) Manual, except to the extent
        the Program Secretarial Officer (PSO) responsible for a site,
        facility or program approves an implementation plan that includes a
        schedule for implementation of a specific provision after 12-1-92.

6.  REFERENCES.  The following documents provide useful information for
    implementing and/or a basis for the requirements of this Order.

    a.  DOE 1324.2A, RECORDS DISPOSITION, of 9-13-88, which prescribes
        policies, procedures, standards, and guidelines for the orderly
        disposition of records of the DOE and its operating contractors.

    b.  DOE 5000.3A, OCCURRENCE REPORTING AND PROCESSING OF OPERATIONS
        INFORMATION, of 5-30-90, which establishes a DOE system for
        identification, categorization, notification, analysis, reporting,
        followup, and closeout of occurrences.

    c.  DOE 5480.1B, ENVIRONMENT, SAFETY, AND HEALTH PROGRAM FOR DEPARTMENT
        OF ENERGY OPERATIONS, of 9-23-86, which outlines environmental,
        safety, and health protection policies and responsibilities.

    d.  DOE 5480.4, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
        STANDARDS, of 5-15-84, which identifies mandatory and recommended
        environment, safety, and health standards.

    e.  DOE 5480.5, SAFETY OF NUCLEAR FACILITIES, of 9-23-86, which
        establishes DOE's nonreactor nuclear facility safety program.

    f.  DOE 5480.6, SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS,
        of 9-23-86, which establishes DOE reactor safety program.

    g.  DOE 5480.15, DEPARTMENT OF ENERGY LABORATORY ACCREDITATION PROGRAM
        FOR PERSONNEL DOSIMETRY, of 12-14-87, which defines requirements for
        participation in the DOE Laboratory Accreditation Program.

    h.  DOE 5482.1B, ENVIRONMENT, SAFETY, AND HEALTH APPRAISAL PROGRAM, of
        9-23-86, which establishes the DOE environmental protection, safety,
        and health protection appraisal program.

    i.  DOE 5484.1, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
        INFORMATION REPORTING REQUIREMENTS, of 2-24-81, which establish
        procedures for investigation of accidents having environmental
        protection, safety, or health protection significance.

    j.  DOE Orders in the 5500 series that outline responsibilities for
        emergency preparedness.

    k.  DOE 5700.6C, QUALITY ASSURANCE, of 8-21-91, which sets forth actions
        for establishing, implementing, and maintaining actions to assure
        quality achievement in DOE programs.

    l.  DOE 6430.1A, GENERAL DESIGN CRITERIA, of 4-6-89, which provides
        general design criteria for the acquisition of DOE facilities.

    m.  DOE publication DOE/EH-0026, "Handbook for the Department of Energy
        Laboratory Accreditation Program for Personnel Dosimetry Systems,"
        which provides operating procedures for the program and is available
        from the National Technical Information Service.

    n.  DOE publication DOE/EH-0027, "Department of Energy Standard for the
        Testing of Personnel Dosimetry Systems," which provides the
        performance testing criteria used to accredit personnel dosimeters
        and is available from the National Technical Information Service.

    o.  DOE publication PNL-6577, "Health Physics Manual of Good Practices
        for Reducing Radiation Exposure to Levels that are As Low As
        Reasonably Achievable (ALARA)," of 7-88, that provides contractor
        personnel with general guidance regarding programs and techniques to
        reduce radiation exposure to as low as reasonably achievable.  This
        document may be purchased from the National Technical Information
        Service.

    p.  DOE publication DOE/EH-0070, "External Dose-Rate Conversion Factors
        for Calculation of Dose to the Public," of 7-88, which provides
        conversion factors for use in calculating dose from radionuclides
        external to the body and is available from the National Technical
        Information Service.

    q.  DOE publication DOE/EH-0071, "Internal Dose Conversion Factors for
        Calculation of Dose to the Public," of 7-88, which provides
        conversion factors for use in calculating dose from radionuclides in
        the body and is available from the National Technical Information
        Service.

    r.  Nuclear Energy Agency report, "Assessment and Recording of Radiation
        Dose to Workers," of 1986, which provides recommended technical
        procedures for a unified approach for dose assessment and recording.
        This document is available from the Organization for the Economic
        Cooperation and Development, Paris, France.

    s.  The following reports of the National Council on Radiation
        Protection and Measurements (NCRP) available from the National
        Council on Radiation Protection and Measurements, Bethesda,
        Maryland.

        (1)  NCRP Report 84, "General Concepts for the Dosimetry of
             Internally Deposited Radionuclides."

        (2)  NCRP Report 87, "Use of Bioassay Procedures for Assessment of
             Internal Radionuclide Deposition."

        (3)  NCRP Report 91, "Recommendations on Limits for Exposure to
             Ionizing Radiation."

    t.  The following International Commission on Radiological Protection
        (ICRP) publications available from Pergamon Press, Elmsford, New
        York.

        (1)  ICRP Publication 23, "Reference Man Anatomical Physiological
             and Metabolic Characteristics."

        (2)  ICRP Publication 26, "Recommendations of the International
             Commission on Radiological Protection."

        (3)  ICRP Publication 30, "Limits for Intakes of Radionuclides by
             Workers."

        (4)  ICRP Publication 32, "Limits for Inhalation of Radon Daughters
             by Workers."

        (5)  ICRP Publication 37, "Cost-Benefit Analysis in the Optimization
             of Radiation Protection."

        (6)  ICRP Publication 48, "The Metabolism of Plutonium and Related
             Elements."

    u.  Environmental Protection Agency standards:

        (1)  "Radiation Protection Guidance to the Federal Agencies for
             Occupational Exposure," Federal Register, Vol 52, No. 17, 1987.

        (2)  Title 40 CFR Part 141, "National Interim Primary Drinking Water
             Regulations (Safe Drinking Water Act)," which prescribes
             radionuclide concentration limits for public drinking water.

    v.  The following American National Standards Institute (ANSI) standards
        available from American National Standards Institute, New York, New
        York.

        (1)  N2.1-1971, "Radiation Symbol."

        (2)  N2.3-1979, "Immediate Evacuation Signal for Use in Industrial
             Installations Where Radiation Exposures May Occur."

        (3)  N8.3-1979, "Criticality Accident Alarm."

        (4)  N12.1-1971, "Fissile Material Symbol."

        (5)  N13.1-1982, "Guide to Sampling Airborne Radioactive Materials
             in a Nuclear Facility."

        (6)  N13.2-1982, "Administrative Practices in Radiation Monitoring
             (A Guide for Management)."

        (7)  N13.3-1981, "Dosimetry for Criticality Accidents."

        (8)  N13.4-1983, "Specifications of Portable X- or Gamma Radiation
             Survey Instruments."

        (9)  N13.5-1982, "Performance Specifications for Direct Reading and
             Indirect Reading Pocket Dosimeters for X- and Gamma Radiation."

       (10)  N13.6-1972, "Practice for Occupational Radiation Exposure
             Record Systems."  (Reaffirmed in 1982)

       (11)  N13.15-1981, "Performance of Personnel Thermoluminescence
             Dosimetry Systems."

       (12)  N317-1985, "Performance Criteria for Instrumentation Used for
             Inplant Plutonium Monitoring."

       (13)  N319-1984, "Personnel Neutron Dosimeters (Neutron Energies Less
             Than 20 MeV)."

       (14)  N320-1985, "Performance Specifications for Reactor Emergency
             Radiological Monitoring Instrumentation."

       (15)  N322-1983, "Inspection and Test Specifications for Direct and
             Indirect Reading Quartz Fiber Pocket Dosimeters."

       (16)  N323-1983, "Radiation Protection Instrumentation Test and
             Calibrations."

       (17)  N510-1980, "Testing of Nuclear Air Cleaning Systems."

       (18)  Z88.2-1980, "Practices for Respiratory Protection."

    w.  Executive Order 12344, "Naval Nuclear Propulsion Program," of
        2-1-82, which establishes the responsibilities of the Director,
        Naval Nuclear Propulsion Program for the joint DOE/Navy Naval
        Nuclear Propulsion Program.

7.  RESPONSIBILITIES AND AUTHORITIES.

    a.  The Secretary.  Many provisions in this Order permit and/or
        necessitate the exercise of discretion and/or judgment in carrying
        out the requirements of the Order.  In those instances, the
        determination of whether, in the exercise of such discretion and/or
        judgment, the requirements of this Order were complied with, rests
        initially with the relevant Departmental authority and ultimately,
        with the Secretary.  The Secretary retains the sole and final
        authority to determine what acts are necessary to comply with this
        Order.  This authority may be delegated by the Secretary as
        appropriate.

    b.  In addition to those responsibilities and authorities contained in
        DOE 5480.1B, the following responsibilities and authorities are
        assigned, as follows:

        (1)  Assistant Secretary for Environment, Safety and Health (EH-1):

             (a)  Develops DOE radiation protection policy and requirements;
                  and

             (b)  Approves, if warranted, requests for specific exceptions
                  to this Order.

        (2)  Program Assistant Secretaries.  Implement DOE radiation
             protection policy and requirements in programs and facilities
             for which they have programmatic or custodial responsibility
             and through the DOE contractors for which they have contract
             administration.

        (3)  Heads of Field Organizations.

             (a)  Implement the provisions of this Order for activities for
                  which they have direct or custodial responsibility and
                  through the DOE contractors for which they have contract
                  administration.

             (b)  Process specific requests for exceptions to this Order
                  [See paragraph 7b(1)(b)].

             (c)  In emergency situations, where immediate decisions and
                  actions are required, approve, if warranted, requests for
                  exceptions from the requirements of this Order and report
                  such action in accordance with DOE 5484.1.

             (d)  Temporarily suspend the requirements of this Order when
                  doing so is, in their judgment, necessary to minimize
                  danger to life or property or to protect public health or
                  safety.  Whenever this provision is invoked, such
                  suspension and the reason therefore is to be reported to
                  EH-1 at the earliest practicable time.

        (4)  Deputy Assistant Secretary for Naval Reactors.  Executive Order
             12344, statutorily prescribed by PL 98-525 (42 USC 7158 note),
             establishes the responsibilities of the Director, Naval Nuclear
             Propulsion Program for the joint DOE/Navy Naval Nuclear
             Propulsion Program.  Within the Department, the Director (who
             is also the Deputy Assistant Secretary for Naval Reactors) is
             responsible for prescribing and enforcing standards and
             regulations for control of radiation and radioactivity as they
             affect the safety and health of workers, operators, and the
             general public for Naval Reactors facilities and activities.
             Accordingly, the provisions of this Order do not apply to Naval
             Reactors facilities and activities except as determined by the
             Director.

8.  DEFINITIONS.

    a.  Annual Limit on Intake (ALI).  The quantity of a single radionuclide
        which, if inhaled or ingested in 1 year, would irradiate a person,
        represented by reference man (ICRP Publication 23) to the limiting
        value for control of the workplace (paragraph 9j(2)).

    b.  As Low As Reasonably Achievable (ALARA).  An approach to radiation
        protection to control or manage exposures (both individual and
        collective to the workforce and general public) as low as social,
        technical, economic, practical, and public policy considerations
        permit.  As used in this Order, ALARA is not a dose limit but a
        process, which has the objective of dose levels as far below
        applicable limits of the Order as reasonably achievable.

    c.  Area Terms.

        (1)  Controlled Area.  Any area to which access is controlled in
             order to protect individuals from exposure to radiation and
             radioactive materials.

        (2)  Radiological Area.  Any area within a controlled area where an
             individual can receive a dose equivalent greater than 5 mrem
             (50 microsieverts) in 1 hour at 30 cm from the radiation source
             or any surface through which the radiation penetrates, or where
             airborne radioactive concentrations greater than 1/10 of the
             derived air concentrations are present (or are likely to be),
             or where surface contamination levels greater than those
             specified in Attachment 2 of this Order are present.

    d.  Derived Air Concentration (DAC).  Quantity obtained by dividing the
        ALI for any given radionuclide by the volume of air breathed by an
        average worker during a working year (2.4 x 10/3 m/3).

    e.  Dose Terms.

        (1)  Absorbed Dose (D).  The energy imparted to matter by ionizing
             radiation per unit mass of irradiated material at the place of
             interest in that material.  The absorbed dose is expressed in
             units of rad (or gray) (1 rad = 0.01 gray).

        (2)  Dose Equivalent (H).  The product of absorbed dose (a) in rads
             (or gray) in tissue, a quality factor (Q), and other modifying
             factors (N).  Dose equivalent (H) is expressed in units of rem
             (or sievert).

        (3)  Annual Dose Equivalent.  The dose equivalent received in a
             year.  Annual dose equivalent is expressed in units of rem (or
             sievert).

        (4)  Shallow, Deep, and Lens of Eve Dose Equivalent.  The dose
             equivalent at the respective depths of 0.007 cm, 1.0 cm, and
             0.3 cm in tissue.

        (5)  Effective Dose Equivalent (HE).  The sum over specified tissues
             of the products of the dose equivalent in a tissue (Ht) and the
             weighting factor (Wt) for that tissue, i.e., HE = Wt Ht.  The
             effective dose equivalent is expressed in units of rem (or
             sievert).

        (6)  Annual Effective Dose Equivalent.  The effective dose
             equivalent received in a year.  The annual effective dose
             equivalent is expressed in units of rem (or sievert).

        (7)  Committed Dose Equivalent.  The calculated dose equivalent
             projected to be received by a tissue or organ over a 50-year
             period after an intake of radionuclide into the body.  It does
             not include contributions from external dose.  Committed dose
             equivalent is expressed in units of rem (or sievert).

        (8)  Committed Effective Dose Equivalent (HE, 50) The sum of the
             committed dose equivalents to various tissues in the body, each
             multiplied by its weighting factor.  It does not include
             contributions from external dose.  Committed effective dose
             equivalent is expressed in units of rem (or sievert).

        (9)  Collective Dose Equivalent.  The sum of the dose equivalents of
             all individuals in an exposed population.  Collective dose
             equivalent is expressed in units of person-rem (or
             person-sievert).

       (10)  Collective Effective Dose Equivalent.  The sum of the effective
             dose equivalents of all individuals in an exposed population.
             Collective effective dose equivalent is expressed in units of
             person-rem (or person-sievert).

       (11)  Cumulative Annual Effective Dose Equivalent.  The sum of the
             annual effective dose equivalents recorded for an individual
             for each year of employment at a DOE or DOE contractor facility
             since the effective date of this Order.

       (12)  Weighting Factor (Wt).  Is used in the calculation of annual
             and committed effective dose equivalent to equate the risk
             arising from the irradiation of tissue T to the total risk when
             the whole body is uniformly irradiated.  The weighting factors
             as defined in ICRP Publication 26 and NCRP Report 91 are:

                  Organs or Tissues            Weighting Factor

                  Gonads                            0.25
                  Breasts                           0.15
                  Red Bone Marrow                   0.12
                  Lungs                             0.12
                  Thyroid                           0.03
                  Bone Surf                         0.03
                  Remainder \1                      0.30

                  -----------------------
                  \1 "Remainder" means the five other organs or tissue with
                  the highest dose (e.g., liver, kidney, spleen, thymus,
                  adrenal, pancreas, stomach, small intestine, upper large
                  intestine or lower large intestine).  The weighting
                  factor for each remainder organ or tissue is 0.06.  The
                  extremities, skin, and lens of the eye are excluded from
                  the "remainder" organs or tissue for assessment of
                  effective dose equivalent.

    f.  Extremity.  Extremity includes hands and arms below the elbow or
        feet and legs below the knee.

    g.  Monitoring.  Actions intended to detect and evaluate radiological
        conditions.

    h.  Non-Stochastic Effects.  Effects such as the opacity of the lens of
        the eye for which the severity of the effect varies with the dose,
        and for which a threshold may exist.

    i.  Occupational Worker.  An individual who is either a DOE or DOE
        contractor employee; an employee of a subcontractor to a DOE
        contractor; or an individual who visits to perform work for or in
        conjunction with DOE or utilizes DOE facilities.

    j.  Quality Factor (Q).  A modifying factor that is employed to derive
        dose equivalent from absorbed dose (paragraph 9f(5)).

    k.  Radiation Worker.  An occupational worker whose job assignment
        requires work on, with, or in the proximity of radiation producing
        machines or radioactive materials, and/or who has the potential of
        being routinely exposed above 0.1 rem (0.001 sievert) per year,
        which is the sum of the annual effective dose equivalent from
        external irradiation and the committed effective dose equivalent
        from internal irradiation.

    l.  Stochastic Effects.  Malignant and hereditary disease 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.

9.  REQUIREMENTS FOR RADIATION PROTECTION OF OCCUPATIONAL WORKERS, UNBORN
    CHILD, STUDENTS, MINORS, AND ONSITE MEMBERS OF THE PUBLIC.

    a.  Maintaining Radiation Exposures As Low As Reasonably Achievable
        (ALARA).  It is DOE's policy that exposures to radiation resulting
        from DOE operations be maintained within limiting values given in
        paragraph 9 and as far below all limiting values as reasonably
        achievable.  This policy applies to annual, committed, and
        cumulative dose equivalents.  Plans and programs used to assure that
        occupational radiation exposures are maintained ALARA shall be
        documented.  The DOE publication PNL-6577, "Health Physics Manual of
        Good Practices for Reducing Radiation Exposure to Levels that are As
        Low As Reasonably Achievable (ALARA)," presents a guide on useful
        practices for achieving the objective of the ALARA process.

    b.  Radiation Protection Standards for Internal and External Exposure
        for Occupational Workers.  The exposure of an Occupational worker to
        radiation resulting from routine DOE activities shall not cause the
        limiting values for assessed dose specified herein and summarized in
        Figure 1 to be exceeded.  Continued exposure of any worker over a
        substantial portion of a working lifetime at or near the limiting
        values for assessed dose to individual workers should be avoided.
        (Note:  Natural background and therapeutic and diagnostic medical
        exposures are not to be included in dose records or in assessment of
        dose against limiting values.)

        (1)  Stochastic Effects.  The limiting value of annual effective
             dose equivalent from both internal and external sources
             received in any year by an occupational worker is 5 rem (0.05
             sievert).

        (2)  Non-Stochastic Effects.  The limiting value of annual dose
             equivalent received in any year by an Occupational worker, for
             individual organs and tissue is 15 rem (0.15 sievert) to the
             lens of the eye or 50 rem (0.5 sievert) to any other organ,
             tissue (including the skin of the whole body), or extremity of
             the body.

        (3)  Unborn Child.  The limiting value of annual dose equivalent
             received by the unborn child from the period of conception to
             birth (entire gestation period) as a result of occupational
             exposure of a female occupational worker, who has notified her
             employer in writing that she is pregnant, is 0.5 rem (0.005
             sievert).  Efforts should be made to avoid substantial
             variation above the uniform monthly exposure rate that would
             satisfy this limiting value.  If the dose to the unborn child
             is determined to have already exceeded 0.5 rem (0.005 sievert)
             by the time a worker notifies her employer in writing of her
             pregnancy, the worker shall not be assigned to tasks where
             additional occupational exposure is likely.  The limiting value
             of dose equivalent to the unborn and the assignment of female
             workers (who have declared pregnancy in writing to their
             employer) to tasks where additional occupational exposure is
             not likely does not create a basis for discrimination and
             should be achieved in conformance with the provisions of Title
             VII of the Civil Rights Act of 1964 [See Environmental
             Protection Agency (1) - pages 2829 and 2832 of Federal
             Register, Vol. 52, No. 17, 1987].

    c.  Planned Special Exposure.  Planned special exposures (non-emergency)
        that would result in an individual exceeding the annual effective
        dose equivalent limit are allowed in highly unusual situations where
        alternatives which would avoid higher exposures are unavailable or
        impractical.  Such planned special exposures, together with the
        annual occupational dose received or anticipated to be received in
        that year, shall not exceed 2 times the annual effective dose
        equivalent limit specified in paragraph 9b(1).  Planned special
        exposures require the approval of the Head of the DOE Field
        Organization.  A second planned special exposure to the same
        individual at any time requires the approval of the Assistant
        Secretary for Environment, Safety, and Health (EH-1).  Documentation
        of planned special exposures shall be maintained in an individual's
        occupational exposure history.

    d.  Radiation Protection Standards for Internal and External Exposure to
        Minors and Students.

        (1)  Minors.  An individual under age 18 shall neither be employed
             in, nor allowed to enter, controlled areas in such a manner
             that he or she exceeds a limiting value of 0.1 rem (0.001
             sievert) per year from the sum of the committed effective dose
             equivalent from internal irradiation and the annual effective
             dose equivalent from external irradiation.

        (2)  Students.  Students under age 18 shall not be exposed to
             radiation during individually authorized educational activities
             such that he or she exceeds a limiting value of 0.1 rem (0.001
             sievert) per year from the sum of the committed effective dose
             equivalent from internal irradiations and the annual effective
             dose equivalent from external irradiation.  This exposure shall
             be considered a part of the limit for workers under age 18 and
             not supplemental to it [i.e., where individuals underage 18 are
             exposed to radiation both as a student and as a minor in a
             year, their exposure as a student shall be added to their
             exposure as a minor and the total is not to exceed the single
             limiting value of 0.1 rem for minors].

___________________________________________________________________________
|                                                                         |
| Stochastic Effects              5 rem (annual effective dose            |
| ------------------              equivalent                              |
|                                                                         |
| Non-Stochastic Effects                                                  |
| ----------------------                                                  |
|   Lens of eye                   15 rem (annual dose equivalent)         |
|                                                                         |
|   Extremity                     50  rem (annual dose equivalent)        |
|                                                                         |
|   Skin of the whole body        50  rem (annual dose equivalent)        |
|                                                                         |
|   Organ or tissue               50  rem (annual dose equivalent)        |
|                                                                         |
| Unborn Child                                                            |
| ------------                                                            |
|   Entire gestation period       0.5 rem (annual dose equivalent)        |
|                                                                         |
|_________________________________________________________________________|
                               Figure 1
                      Radiation Protection Standards
            Limiting Values for Assessed Dose from Exposure of
                    Occupational Workers to Radiation


    e.  Radiation Protection Standards for Public Entering a Controlled
        Area.  The effective dose equivalent received by any member of the
        public resulting from exposure during direct onsite access at a DOE
        facility shall not exceed a limiting value of 0.1 rem (0.001
        sievert) per year from the committed effective dose equivalent from
        internal irradiation plus the effective dose equivalent from any
        external irradiation.  In addition, exposures shall not cause a dose
        equivalent to any tissue (including the skin and the lens of the
        eye) to exceed 5 rem (0.05 sievert) per year for any member of the
        public.  Guidance for entry during emergency conditions is provided
        in paragraph 9p of this Order.

    f.  Procedural Requirements.

        (1)  Combining Internal and External Dose Equivalent.  The annual
             effective dose equivalent to an individual shall be determined
             by summing the annual effective dose equivalents from
             internally deposited radionuclides and from external exposure
             to radioactive material and/or radiation generating devices
             resulting from DOE activities.  When in-vivo and/or in-vitro
             measurements confirm the retention of radionuclides in the
             body, with respect to evaluating conformance with the limiting
             value for occupational exposure, the annual effective dose
             equivalent due to all radionuclides retained in the body from
             these intakes shall be assessed for as long as the annual
             effective dose equivalent is 10 mrem or greater.  Exposures to
             the skin, extremities, and lens of the eye are not included in
             the determination of the annual effective dose equivalent.  For
             uniform external irradiation of the whole body, a weighting
             factor (Wt) equal to one may be used.  This whole body dose is
             to be measured in accordance with the provisions in paragraph
             9g(1).  Non-uniform external and internal irradiation values of
             Wt for organs and tissues are defined in paragraph 8e(12).

        (2)  Non-Uniform Exposure to Skin.  For non-uniform exposures to
             skin from x rays, beta radiation, or skin contamination, one of
             the following assessments shall be made and recorded:

             (a)  When the area of skin exposed is >100 cm/2 the maximum
                  value of dose averaged over any area of 100 cm/2 is to be
                  assessed, recorded, and included in the annual skin
                  (shallow) dose equivalent.

             (b)  When the area of skin exposed is >10 cm/2 but <100 cm/2
                  the dose equivalent to that tissue is to be determined by:

                                       H = fD

                  where:  D is the maximum dose averaged over a 1 cm/2 of
                  skin and f is the fraction of skin exposed compared to 100
                  cm/2.  In no case shall an "f" of <0.1 be used.  This
                  value of dose is to be recorded and included in the annual
                  skin (shallow) dose equivalent.

             (c)  When the area of skin exposed is <10 cm/2 the maximum
                  value of dose averaged over any 1 cm/2 is to be assessed
                  and recorded in the individual's occupational exposure
                  history as a special entry but is not to be included in
                  the annual skin (shallow) dose equivalent.

        (3)  Emergency or Accidental Exposures.  When an occupational worker
             has been exposed to radiation in excess of the limits specified
             in this Order as a result of an unplanned or accidental
             situation, the decision to allow the worker to return to work
             in a radiological area shall be made by operating management
             based on advice from health physics and medical personnel and
             the concurrence of the worker and shall be subject to the
             approval of the DOE field organization manager.  The dose
             received in an unplanned or accidental situation is to be
             documented in the radiation exposure record of the exposed
             individual pursuant to paragraph 9m(2) and reported pursuant to
             DOE 5484.1.  The operating contractor is to verify to the head
             of the responsible field organization that the conditions under
             which the emergency or accidental exposures were received have
             been eliminated.  The resumption of operations following an
             emergency or accidental exposure in excess of the occupational
             limits specified in this Order shall be subject to the approval
             of the head of the responsible field organization.
             Investigations and reporting shall be conducted pursuant to DOE
             5484.1 and DOE 5000.3.

        (4)  Air and Water Concentration Guides.

             (a)  Air.  Derived air concentration (DAC) values for control
                  of the workplace are given in Attachment 1.  They were
                  derived from the ICRP Publication 30 values for committed
                  effective dose equivalent values, translated to
                  conventional U.S. units of rem and curie.  The ICRP
                  Publication 23 recommended annual inhalation volume for
                  male workers (40 hr/wk, 50 wk/yr) was assumed to be 2400
                  m/3.  The DAC values or other air concentration values shall
                  not be used for the calculation of internal dose
                  equivalent received by a worker except for unusual
                  circumstances where bioassay data is unavailable or
                  inadequate.

             (b)  Water.  Concentrations of radionuclides in drinking water
                  in controlled areas shall not exceed the standards given
                  in 40 CFR Part 141.

        (5)  Quality Factors.  The dose equivalent limits specified in this
             chapter are expressed in terms of rem; this requires that the
             absorbed dose (expressed in rads) be multiplied by an
             appropriate quality factor (Q).  The quality factors to be used
             for determining dose equivalent in rem are shown in Figures 2
             and 3.

_________________________________________________________________________
|   RADIATION TYPE                                  QUALITY FACTOR (Q)* |
|-----------------------------------------------------------------------|
|    X-rays, gamma rays, positrons,                         1           |
|    electrons (including tritium beta particles)                       |
|                                                                       |
|    Neutrons, <= 10 keV                                    3           |
|                                                                       |
|    Neutrons, > 10 keV                                    10           |
|                                                                       |
|    Protons and singly-charged particles                  10           |
|    of unknown energy with rest mass                                   |
|    greater than one atomic mass unit                                  |
|                                                                       |
|    Alpha particles and multiple-charged                  20           |
|    particles (and particles of unknown                                |
|    charge) of unknown energy                                          |
|                                                                       |
| --------------------                                                  |
|                                                                       |
| *  Where spectral data is sufficient to identify the energy of the    |
|    neutrons, the Q values in Figure 3 may be used.                    |
|_______________________________________________________________________|
                                 Figure 2
                             Quality Factors

_________________________________________________________________________
|                                           _                 NEUTRON   |
|          NEUTRON ENERGY                   Q              FLUX DENSITY |
|-----------------------------------------------------------------------|
|                MeV                                       cm-2  s-1    |
|                                                                       |
|          2.5 x 10-8 (thermal)              2                680       |
|          1   x 10-7                        2                680       |
|          1   x 10-6                        2                560       |
|          1   x 10-5                        2                560       |
|          1   X 10-4                        2                580       |
|          1   x 10-3                        2                680       |
|          1   x 10-2                        2.5              700       |
|          1   x 10-1                        7.5              115       |
|          5   x 10-1                       11                 27       |
|              1                            11                 19       |
|              2.5                           9                 20       |
|              5                             8                 16       |
|              7                             7                 17       |
|             10                             6.5               17       |
|             14                             7.5               12       |
|             20                             8                 11       |
|             40                             7                 10       |
|             60                             5.5               11       |
|          1   x 10 2                        4                 14       |
|          2   x 10 2                        3.5               13       |
|          3   x 10 2                        3.5               11       |
|          4   x 10 2                        3.5               10       |
|                                                                       |
|                        _ *             __                             |
|  Mean quality factors, Q, and values of neutron flux density which,   |
|  in 40 hours, result in a maximum dose equivalent of 100 mrem.        |
|                                                                       |
|  * Maximum value of Q in a 30-cm dosimetry phantom.                   |
|_______________________________________________________________________|
                                Figure 3
                       Quality Factors for Neutrons


    g.  Monitoring.  Occupational workers shall be monitored, as
        appropriate, to demonstrate compliance with the radiation protection
        standards in paragraph 9b and to estimate the dose equivalents
        received from external and internal sources of radiation.
        Workplaces shall be routinely monitored, as appropriate, for
        identification and control of potential exposure sources.

        (1)  External Radiation.  Personnel dosimetry programs shall be
             adequate to demonstrate compliance with the radiation
             protection standards provided in paragraph 9b.  Personnel
             dosimeters shall be routinely calibrated and maintained and
             shall meet the requirements of the DOE Laboratory Accreditation
             Program for Personnel Dosimetry as specified in DOE 5480.15.
             Personnel dosimetry shall be provided to radiation workers who
             have the potential to exceed in a year any one of the following
             from external sources:

             (a)  One hundred mrem (0.001 sievert) annual effective dose
                  equivalent to the whole body.

             (b)  Five rem (0.05 sievert) annual dose equivalent to the
                  skin.

             (c)  Five rem (0.05 sievert) annual dose equivalent to any
                  extremity.

             (d)  One and a half rem (0.015 sievert) annual dose equivalent
                  to the lens of the eye.

        (2)  Internal Radiation.  Internal dose evaluation programs
             (including routine bioassay programs) shall be adequate to
             demonstrate compliance with the radiation protection standards
             in paragraph 9b.  Such programs are required for radiation
             workers exposed to surface or airborne radioactive
             contamination where the worker could receive 0.1 rem (0.001
             sievert) annual effective dose equivalent from all intakes of
             all radionuclides from occupational sources, or if any organ or
             tissue dose equivalent could exceed 5 rem (0.05 sievert) annual
             dose equivalent.

        (3)  Workplace.

             (a)  Air Monitoring.  Ambient air monitoring shall be performed
                  in occupied areas with the potential to exceed 10 percent
                  of any derived air concentration values given in
                  Attachment 1.  Representative ambient air monitoring
                  samples should be taken in strategic locations to detect
                  and evaluate airborne radioactive material at work
                  locations.  Data obtained from air monitoring shall be
                  used for assessing the control of airborne radioactive
                  material in the workplace; it should not normally be used
                  to evaluate the dose equivalent to radiation workers.  Air
                  monitors shall be routinely calibrated and maintained, and
                  should be capable of measuring one DAC when averaged over
                  8 hours (8 DAC-hours).

             (b)  Radiation Monitoring.  Appropriate stationary (area)
                  and/or portable radiation instruments shall be available
                  and used to measure dose rates for the purpose of
                  controlling exposure to radiation.  These instruments
                  shall be routinely calibrated and maintained.  The
                  combination of instruments used shall provide capability
                  to measure types of radiation (neutron, gamma, beta, or
                  x-radiation) and dose rates characteristic of that which
                  could be encountered at that facility.

        (4)  Contamination Control and Monitoring.  Appropriate instruments
             and techniques shall be used to provide contamination
             monitoring and control as described below:

             (a)  Workplace Surfaces Outside Radiological Areas should be
                  maintained essentially free of removable contamination but
                  in any case contamination shall not exceed the levels
                  defined in Attachment 2.  Acceptable levels for total
                  (fixed plus removable) contamination are also listed in
                  Attachment 2.

             (b)  Workplace Surfaces in Radiological Areas shall be posted
                  (paragraph 9k) and controlled, as appropriate.  The degree
                  of control from simple (e.g., shoe covers and lab coat) to
                  complex (e.g., multiple layers of protective clothing and
                  respiratory protection) should be based on the specific
                  contaminants present and the level of contamination.

             (c)  Personnel and Personal Property Contamination Monitoring
                  shall be provided, as appropriate, and used immediately
                  prior to or after exits from radiological areas
                  established to control surface or airborne radioactive
                  contamination.  If monitoring is performed after the exit,
                  appropriate controls shall be implemented to prevent the
                  loss of control of contamination.  Detectable
                  contamination on personnel and personal property should be
                  removed by appropriate decontamination methods.

    h.  Methods of Estimating Dose Equivalent.  Methods of estimating the
        dose equivalent from external and internal sources of radiation are
        to be appropriate to the workplace conditions and consistent with
        the recommendations of NCRP, ICRP, and EPA.

    i.  Releases of Materials and Equipment from Radiological Areas.  The
        following requirements apply for the release of materials and
        equipment from radiological areas for conditional use in controlled
        areas.  In all cases, contaminated property shall be cleaned as
        thoroughly as practical before release.  These requirements are not
        applicable to the release of materials or equipment for unrestricted
        use since such use could result in exposure to the general public.
        (NOTE:  Requirements contained in this Order do not pertain to
        either induced radioactivity or decontamination and decommissioning
        release limits.)

        (1)  Material and equipment in radiological areas established to
             control surface or airborne radioactive material shall be
             treated as radioactive material and shall not be released from
             radiological areas to controlled areas if any of the following
             conditions exist:

             (a)  Measurements of accessible surfaces show that either the
                  total or removable contamination levels exceed the guides
                  specified in Attachment 2; or

             (b)  Prior use suggests that the contamination levels on
                  inaccessible surfaces are likely to exceed the guides
                  specified in Attachment 2.

        (2)  Material and equipment exceeding the total and removable
             contamination levels specified in Attachment 2 shall be
             conditionally released for movement onsite from one
             radiological area for immediate placement in another
             radiological area only if appropriate monitoring and control
             procedures are established and exercised.

        (3)  Under exceptional conditions, material and equipment with fixed
             contamination that exceed the limits specified in Attachment 2
             may be released for use in controlled areas outside
             radiological areas.  As a condition of such release, the
             materials shall be routinely monitored, clearly labeled and/or
             tagged to alert personnel of the contaminated status, and have
             appropriate administrative procedures established and exercised
             to maintain control of these items.

        (4)  The records for release of potentially contaminated material
             and equipment shall describe the property, the date of the last
             monitoring operation, the identity of the individual who
             performed the monitoring operation, the type and identification
             number of the monitoring instrument used, and the results of
             the monitoring operation.

    j.  Design and Control.  Radiation exposure rates in controlled
        workplace areas should be reduced to as low as reasonably achievable
        levels by proper facility design and control.  The primary means for
        maintaining exposures as low as reasonably achievable are to be
        through physical controls, e.g., confinement, ventilation, remote
        handling, and shielding.  Administrative controls and procedural
        requirements are to be considered supplemental means to achieve
        control.

        (1)  Design.  During the design of facilities, the following
             objectives shall be applied:

             (a)  Optimization.  Optimization principles, as discussed in
                  ICRP Publication 37, are to be utilized in developing and
                  justifying facility design and physical controls.

             (b)  External Radiation Exposure.  The design objectives for
                  personnel exposure from external sources of radiation in
                  continuously occupied controlled areas are ALARA and not
                  exceeding 0.5 mrem (5 microsieverts) per hour on average.
                  The design objectives for exposure rates for potential
                  exposure to a radiation worker where occupancy is
                  generally not continuous are ALARA and not exceeding 20
                  percent of the applicable standard in paragraphs 9b(1) and
                  (2).

             (c)  Internal Radiation Exposure.  As a design objective,
                  exposure of personnel to inhalation of airborne
                  radioactive materials is to be avoided under normal
                  operating conditions to the extent reasonably achievable.
                  This will normally be accomplished by confinement and
                  ventilation.

             (d)  Maintenance.  Decontamination, and Decommissioning.  Ease
                  of maintenance and decontamination and decommissioning is
                  to be considered in facility design and selection of
                  materials.

        (2)  Control.  During routine operations, the combination of design
             and control procedures shall provide that, with respect to the
             radiological workplace, the anticipated magnitude of the
             prospective committed effective dose equivalent from intakes
             plus any effective dose equivalent from external exposure will
             not exceed 5 rem (0.05 sievert) in a year, and the anticipated
             magnitude of the committed dose equivalent to any organ or
             tissue from intakes plus any dose equivalent from external
             exposure will not exceed 50 rems (0.5 sievert) in a year.
             Compliance with these requirements shall be demonstrated
             through appropriate workplace monitoring pursuant to the
             provisions of paragraph 9g(3).

    k.  Posting and Labeling.  Areas in DOE nuclear facilities shall be
        posted in accordance with the provisions given below.  Radioactive
        material and/or its container shall be individually labeled where
        normal posting of the area and control of the material would not
        provide adequate protection.  The design of signs, labels, and the
        radiation symbol shall conform to ANSI N12.1-1971 and ANSI
        N2.1-1971.  The background color is to be yellow; the symbol color
        may be black or magenta.

        (1)  Controlled Area.  The access to any controlled area where
             radioactive materials or elevated radiation fields may be
             present shall be clearly and conspicuously posted as a


             controlled area.  The type of sign used may be selected by
             the contractor with the approval of the field organization
             to avoid conflict with local security requirements.

        (2)  Radiological Area.

             (a)  Posting for External Radiation.  The access to any area
                  where an individual can at anytime during normal
                  operations receive a dose equivalent greater than 5 mrem
                  (50 microsieverts) in 1 hour at 30 centimeters from the
                  radiation source or any surface through which radiation
                  penetrates shall be posted as below.  In addition, the
                  anticipated dose rate or range of dose rates shall be
                  included on or in conjunction with each of the signs, as
                  appropriate.

                  1  "Radiation Area" for any area within a controlled area
                     where an individual can receive a dose equivalent
                     greater than 5 mrem (50 microsieverts) but less than
                     100 mrem (1 millisievert) in 1 hr at 30 cm from the
                     radiation source or from any surface through which the
                     radiation penetrates,

                  2  "High Radiation Area" for any area within a controlled
                     area where an individual can receive a dose equivalent
                     of 100 mrem or greater (0.001 sievert) but less than 5
                     rem (0.05 sievert) in 1 hr at 30 cm from the radiation
                     source or from any surface through which the radiation
                     penetrates, and

                  3  "Very High Radiation Area" for any area within a
                     controlled area where an individual can receive a dose
                     of 5 rem (0.05 sievert) or greater in 1 hour at 30 cm
                     from the radiation source or from any surface through
                     which the radiation penetrates.

             (b)  Posting for Airborne Radioactive Material.  The access to
                  any area where airborne radioactive material
                  concentrations greater than 1/10 of the derived air
                  concentrations (Attachment 1) are present shall be clearly
                  and conspicuously posted with a sign that identifies the
                  radiological conditions which exist (e.g., "Airborne
                  Radioactivity Area").  The type of sign used shall be
                  consistent with the radiation protection control policies
                  established at the facility and may be selected by the
                  contractor with the approval of the field organization.

             (c)  Posting for Surface Contamination.  The access to any area
                  where surface contamination levels greater than 10 times
                  those specified in Attachment 2 are present shall be
                  clearly and conspicuously posted with a sign that
                  identifies the radiological conditions which exist (e.g.,
                  "Contamination Area").  The type of sign used shall be
                  consistent with the radiation control policies established
                  at the facility and may be selected by the contractor with
                  the approval of the field organization.

    l.  Entry Control Program.  An appropriate entry control program shall
        be established for radiological areas.  This should include a buffer
        area prior to entry to a radiological area where appropriate.  The
        level of control should be consistent with the degree of hazard.
        Signs and barricades, control devices on entrances, conspicuous
        visual and/or audible alarms, locked entrance ways, and/or
        administrative procedures should be used as appropriate to ensure
        that personnel entry into radiological areas is controlled.
        Step-off pads and protective clothing shall be required for entry to
        contaminated areas.  For very high radiation areas, the entry
        control program shall include at a minimum one of the following:

        (1)  Control devices on each entrance or access point which function
             automatically to prevent entry when a very high radiation area
             exists; permit entry only after the radiation level is reduced
             below 0.1 rem (0.001 sievert) per hour; and prevent use or
             operation of the radiation source, thereby preventing the
             existence of a very high radiation area, while an individual is
             in the area.

        (2)  A control device which energizes a conspicuous visible or
             audible alarm signal so that the individual entering the very
             high radiation area through a failed control device is aware of
             the radiation level and radiation protection personnel are
             aware of the entry.  Administrative procedures shall define the
             required actions of personnel when alarms are activated.

        (3)  Locked entry ways, except during periods when access to the
             area is required, with positive control over and radiation
             surveys made for the initial entry and periodically as
             necessary.

        (4)  Control devices that will automatically generate audible and
             visible alarm signals to alert personnel in the area before use
             or operation of the radiation source and in sufficient time to
             permit evacuation of the area or the activation of a secondary
             control device which will prevent use or operation of the
             source.

    m.  Records.  As a minimum, the records specified below of the radiation
        protection program and dosimetry records for all individuals for
        whom monitoring is provided shall be generated and maintained,
        commencing with the effective date of this Order.  Information and
        data developed pursuant to this Order shall be retained consistent
        with the requirements of DOE 1324.2A, RECORDS DISPOSITION.

        (1)  ALARA.  Records of ALARA programs shall be maintained by field
             organizations and operating contractors to demonstrate the
             adequacy of the ALARA plans and programs and their
             implementation.

        (2)  Individual Occupational Dose Records.  Individual occupational
             internal and external dose records and records of the programs
             used to assess individual doses shall be generated and
             maintained sufficient to provide appropriate reports to the
             employee, management, and those required by DOE 5484.1.
             Efforts should be made to obtain records of occupational
             exposure received prior to employment at the site.  Records
             should be readily available for all current employees.  As a
             minimum, the following data shall be recorded and retained for
             individuals for whom monitoring, as appropriate, was provided.

             (a)  Internal Exposure.

                  1  Annual effective dose equivalent received during the
                     year from radioactive material deposited in the body;

                  2  Annual dose equivalent to organ or tissue of concern
                     received during the year from radioactive material
                     deposited in the body;

                  3  Committed effective dose equivalent from intakes
                     occurring during the year;

                  4  Committed dose equivalent to organ or tissue of concern
                     from intakes occurring during the year.

             (b)  External Exposure.

                  1  Annual effective dose equivalent from external sources
                     of radiation received during the year.

                  2  Annual dose equivalent to the lens of the eye.

                  3  Annual dose equivalent to the skin.

                  4  Annual dose equivalent to the extremities received
                     during the year, including:  (1) hands and forearm
                     below the elbow and (2) feet and legs below the knee.

             (c)  Summation of Internal and External Dose Equivalents.

                  1  Summation of the annual effective dose equivalents
                     received from external and internal sources during the
                     year.

                  2  Cumulative annual effective dose equivalent received
                     from external and internal sources while employed at
                     the facility, since the effective date of this Order.

             (d)  Programs to Determine Individual Exposures.  Data
                  necessary to support or re-calculate doses at a later date
                  shall be maintained pursuant to Section 4 of ANSI
                  N13.6-1972.

        (3)  Monitoring and Area Control Records.  Records that establish
             the conditions under which individuals were exposed, such as
             facility radiological conditions (as generated by the
             monitoring programs) and surveys for the release of personal
             property and workplace surfaces, shall be kept to provide a
             chronological, historical record pursuant to Section 5 of ANSI
             N13.6-1972.

        (4)  Monitoring Methods Records.  Records shall be kept to document
             the appropriateness, quality, and accuracy of monitoring
             methods, techniques, and procedures in use during any given
             period pursuant to Section 6 of ANSI N13.6-1972.  Changes in
             equipment, techniques, and procedures are to be documented and
             the documents maintained.

        (5)  Training Records.  Training records of plant employees,
             radiation workers, and radiation safety personnel shall be
             retained to document the level of understanding and proficiency
             of personnel who work with radioactive materials.
             Certification of successful completion of training programs and
             performance records should also be retained.

    n.  Reports to Employees.  Records of exposure should be made available
        to all occupational workers on an individual basis and should be
        provided to terminated employees as soon as the data is available
        but within 90 days of termination.  A summary of annual, cumulative,
        and committed effective dose equivalent shall be provided to each
        radiation worker on an annual basis.  The cumulative effective dose
        equivalent is the sum of the annual effective dose equivalents
        recorded for each year of employment since the effective date of the
        Order.  Detailed information concerning a worker's exposure shall be
        made available to the worker upon the request of the worker,
        consistent with the provisions of the Privacy Act (5 USC 552a).

    o.  Radiation Safety Training.

        (1)  All Employees.  All occupational workers who may enter a
             controlled area at a DOE facility shall receive an orientation
             in radiation safety within 1 month of their initial assignment
             to and prior to potential exposure to radiation at that
             facility.  Retraining shall be provided when there are
             significant changes to radiation protection policies and
             procedures which affect general plant employees and should be
             provided every 2 years.  Generic training (not specific to a
             facility) in all or some of the topics listed below may be
             waived provided:  this training has been received at another
             DOE facility; there is provision of proof-of-training in the
             form of a certification document containing the individual's
             name, date of training, and specific topics covered; and an
             appropriate official has certified the training of the
             individual.  The level of training is to be commensurate with
             the employee's job assignment with the initial orientation
             including, but not limited to:

             (a)  The risk of low-level occupational radiation exposure,
                  including cancer and genetic effects;

             (b)  The risk of prenatal radiation exposure;

             (c)  Basic radiation protection concepts;

             (d)  DOE and company radiation protection policies and
                  procedures;

             (e)  Employee and management responsibilities for radiation
                  safety;

             (f)  Emergency procedures.

        (2)  Radiation Workers.  Radiation worker training programs and
             retraining shall be established and conducted at a sufficient
             frequency (not to exceed a period of 2 years) to familiarize
             the worker with the fundamentals of radiation protection and
             the ALARA process.  Training should include both classroom and
             applied training.  The training shall be concurrent with
             assignment as a radiation worker only if the worker is
             accompanied by and under the direct supervision of a trained
             radiation worker; otherwise, the training shall precede
             assignment as a radiation worker.worker.  Generic training (not
             specific to a facility) in all or some of the topics listed
             below may be waived provided:  this training has been received
             at another DOE facility; there is provision of
             proof-of-training in the form of a certification document
             containing the individual's name, date of training, and
             specific topics covered; and an appropriate official has
             certified the training of the individual.  The knowledge of
             radiation safety fundamentals possessed by radiation workers
             should be certified by examination prior to an unsupervised
             assignment.  The training should emphasize procedures specific
             to an individual's job assignment.  Additionally, the level of
             training in the following topics is to be commensurate with
             each worker's assignment:

             (a)  Radioactivity and radioactive decay;

             (b)  Characteristics of ionizing radiation;

             (c)  Man-made radiation sources;

             (d)  Acute effects of exposure to radiation;

             (e)  Risks associated with occupational radiation exposures;

             (f)  Special considerations in the exposure of women of
                  reproductive age;

             (g)  Dose-equivalent limits;

             (h)  Mode of exposure--internal and external;

             (i)  Dose-equivalent determinations;

             (j)  Basic protective measures--time, distance, shielding;

             (k)  Specific plant procedures for maintaining exposure as low
                  as is reasonably achievable;

             (l)  Radiation survey instrumentation--calibration and
                  limitations;

             (m)  Radiation monitoring programs and procedures;

             (n)  Contamination control, including protective clothing and
                  equipment and workplace design;

             (o)  Personnel decontamination;

             (p)  Emergency procedures;

             (q)  Warning signs and alarms;

             (r)  Responsibilities of employees and management;

             (s)  Interaction with radiation protection staff;

             (t)  Operational procedures associated with specific job
                  assignments (e.g., radiation generating machines, glove
                  boxes).

        (3)  Radiation Protection Technician.  Radiation protection
             technician training and retraining programs shall be
             established and conducted at a sufficient frequency, not to
             exceed every 2 years, to familiarize technicians with the
             fundamentals of radiation protection and the proper procedures
             for maintaining exposures ALARA.  This program shall include
             both classroom and applied training and shall precede or be
             concurrent with assignment as a radiation protection technician
             while under the supervision of a trained individual.  The
             knowledge of radiation safety fundamentals possessed by
             radiation protection technicians should be certified by
             examination prior to an unsupervised work assignment.  The
             training program should include the topics listed in the
             paragraph (2) above and should emphasize procedures specific to
             the facility where the technician is assigned.  The level of
             training in each topic is to be commensurate with the
             technician's assignment.

    p.  Guidance and Requirements for Emergency Exposure During Rescue and
        Recovery Activities.

        (1)  Purpose.  This paragraph provides emergency action guidance for
             determining appropriate actions for the rescue and recovery of
             persons and the protection of health and property in the event
             of an emergency.

        (2)  General Considerations.

             (a)  Controlling exposure to radiation during rescue and
                  recovery actions is extremely complex.  Multiple hazards
                  and alternate methods are to be taken into account; and
                  prompt, sound judgment and flexibility of action are
                  crucial to the success of any emergency actions.  The risk
                  of injury to those persons involved in the rescue and
                  recovery activities should be minimized, to the extent
                  practical.  However, the control of radiation exposures
                  should be consistent with the immediate objectives of
                  saving human life, recovering deceased victims, and/or
                  protection of health and property.

             (b)  To avoid unnecessarily restricting action, a rigid upper
                  limit of exposure for lifesaving action is not specified;
                  rather, judgment is left up to the officials in charge to
                  evaluate any proposed action involving further radiation
                  exposure.  The evaluation should consider risk versus
                  benefit, i.e., weighing the risks of radiation insults,
                  actual or potential, against the benefits [social,
                  economic, etc.] to be gained.  Essential elements in risk
                  determinations include potential exposure, biological
                  consequences related to the exposure, and the number of
                  people involved.

             (c)  These instructions also recognize that accident situations
                  involving the saving of lives will require different basis
                  for action than those required to recover deceased victims
                  or to protect property.  In the latter instances, the
                  amount of exposure expected to be received by persons
                  should be controlled as much as possible within
                  occupational exposure limits.

             (d)  Any rescue action that might involve substantial personal
                  risk should be performed by volunteers.  When feasible,
                  volunteers should be evaluated with respect to age and
                  previous exposure history.  Each emergency worker should
                  be advised of the known or anticipated hazards prior to
                  participation by the person onsite having the emergency
                  action responsibility.

        (3)  Emergency Situations.  Specific dose criteria and judgment
             factors are set forth for the three types of emergency action:
             Type 1, saving of human life; Type 2, recovery of deceased
             victims; and Type 3, protection of health and property.

             (a)  Saving of Human Life.

                  1  Attempts to rescue victims of an incident should be
                     regarded in the same context as any other emergency
                     action involving the rescue of victims, regardless of
                     the type of hazard involved.

                  2  If the victim is considered to be alive, the course of
                     action should be determined by the person onsite having
                     the emergency action responsibility.

                  3  The potential amount of exposure to rescue personnel
                     for each specific Type 1 emergency action shall be
                     evaluated by the person onsite having the emergency
                     action responsibility.  The emergency situation should
                     be immediately evaluated and an exposure objective
                     should be established for the rescue mission.  The
                     evaluation of the inherent risks should consider:

                     a  The reliability of the prediction of radiation
                        injury from measured/estimated dose rates.  In this
                        context, consideration should be given to the
                        uncertainties associated with the specific
                        instruments and techniques used to estimate the dose
                        rate.  This is especially crucial when the estimated
                        dose approximates 100 rad (1 gray) or more.

                     b  The effects of acute external and/or internal
                        exposure.

                     c  The capability to reduce risk through physical
                        mechanisms such as the use of protective equipment,
                        remote manipulation equipment, or similar means.

                     d  The probability of success of the rescue action.

             (b)  Recovery of Deceased Victims.

                  1  The recovery of deceased victims should be well
                     planned.  Except as provided in subparagraph 3 below,
                     the amount of radiation exposure received by persons in
                     recovery operations shall be controlled within existing
                     occupational exposure limits.

                  2  When fatalities are located in inaccessible areas due
                     to high direct radiation fields, and when the recovery
                     mission would result in exposure in excess of
                     occupational exposure limits specified in this chapter,
                     special remote recovery devices should be used to
                     retrieve bodies, as appropriate.

                  3  When it is not feasible to recover bodies without
                     personnel entering the area, the official in charge may
                     determine it necessary to exceed the occupational
                     exposure limits specified in this chapter.  The planned
                     exposure of an individual participating in the recovery
                     should not exceed 10 rem (0.1 sievert) per year.

             (c)  Protection of Health and Property.  When the risk
                  (probability and magnitude) of the radiation hazard either
                  bears significantly on the state of health of people, or
                  may result in loss of property, so that immediate remedial
                  action is needed, the following criteria should apply:

                  1  When the official in charge deems it essential to
                     reduce a potential hazard to protect health or prevent
                     a substantial loss of property, a planned exposure
                     objective not to exceed 10 rem (0.1 sievert) per year
                     may be permitted for individuals participating in the
                     operation.  However, under special circumstances, the
                     official in charge of emergency action at the incident
                     may elect to permit volunteers an emergency exposure
                     objective not to exceed 25 rem (0.25 sievert) in any
                     year.

                  2  When the risk of radiation following the incident is
                     such that life might be in jeopardy, or that there
                     might be severe effects on health or the public or loss
                     of property inimical to the public safety, the criteria
                     for saving of human life shall apply.

    q.  Nuclear Accident Dosimetry.  These requirements are applicable to
        DOE contractor installations possessing sufficient quantities and
        kinds of fissile material to potentially constitute a critical mass
        as defined in DOE 5480.5, and where the excessive exposure of
        personnel to radiation from a nuclear accident is possible.

        (1)  Basic Elements.  The basic elements of nuclear accident
             dosimetry shall include:

             (a)  A method to conduct initial "screening" of personnel
                  involved in nuclear accidents to determine if they have
                  received a significant radiation exposure.

             (b)  Methods for analysis of biological materials (including
                  sodium-24 activity in blood and phosphorus-32 activity in
                  hair).

             (c)  A system of fixed units capable of yielding estimated
                  radiation dose and the approximate neutron spectrum at
                  their locations.

             (d)  Personnel dosimeters capable of furnishing sufficient
                  information to determine neutron and gamma dose and/or
                  dose equivalent.

             (e)  Counting facilities to evaluate fixed and/or personnel
                  dosimeters, sodium in blood, and phosphorus in hair.

        (2)  Fixed Nuclear Accident Dosimeter Units.

             (a)  The fixed unit shall be capable of determining neutron
                  dose in rad (gray) with an accuracy of +/- 25 percent.

             (b)  The fixed unit shall be capable of providing the
                  approximate neutron spectrum to permit the conversion of
                  rad to rem.

             (c)  The dose range capability of the neutron components of the
                  fixed unit shill extend from 10 rad (0.1 gray) to about
                  10,000 rad (100 gray).

             (d)  The gamma ray components of the fixed unit shall be
                  capable of measuring fission gamma radiation in the
                  presence of neutrons with an accuracy of approximately +/-
                  20 percent.

             (e)  The dose range capability of the gamma components shall
                  extend from 10 rem (0.10 sievert) to about 10,000 rem (100
                  sievert).

             (f)  The number of dosimeter units needed and their placement
                  will depend on the nature of the operation, structural
                  design of the facility, and accessibility of areas to
                  personnel.  Consideration should be given to the need for
                  remote retrieval mechanisms.  The number and placement of
                  dosimeters shall be periodically re-evaluated, as
                  appropriate, to ensure that modifications to facility
                  design and use have not affected performance.  An analysis
                  that demonstrates that the dosimeters and their placement
                  will satisfy the performance criteria contained in
                  paragraph q shall be documented.  The analysis shall
                  include the number of units, their location, and effect of
                  intervening shielding.  Ease of recovery after a
                  criticality event should be considered in the placement of
                  the fixed units.

        (3)  Personnel Nuclear Accident Dosimeter Units.

             (a)  Personnel Nuclear Accident Dosimeter Units shall be worn
                  by all personnel who enter a controlled area that contains
                  locations requiring an installed criticality alarm system
                  as given in paragraph 11c(3)(g) of DOE 5480.5.

             (b)  Dosimeters worn by the worker should be capable of
                  determining gamma dose from 10 rad (0.1 gray) to 1000 rad
                  (10 gray) with an accuracy of +/- 20 percent and neutron
                  dose from 1.0 rad (0.01 gray) to 1000 rad (10 gray) with
                  an accuracy of +/- 30 percent without dependence upon
                  fixed unit data.

    r.  Contractor Internal Audits.

        (1)  Contractor internal audits of all functional elements of the
             radiation protection program shall be conducted as often as
             necessary but no less frequently than every 3 years.  The audit
             should include, but is not limited to:

             (a)  External dosimetry;

             (b)  Internal dosimetry;

             (c)  Portable and fixed instrumentation;

             (d)  Respirators;

             (e)  Contamination control;

             (f)  Radiological monitoring;

             (g)  ALARA program;

             (h)  Nuclear accident dosimetry;

             (i)  Source material control;

             (j)  X-ray protection;

             (k)  Training;

             (l)  Posting;

             (m)  Records.

        (2)  In conducting such audits, the guidelines set forth in DOE
             5482.1 shall be followed.

BY ORDER OF THE SECRETARY OF ENERGY:



                                        LAWRENCE F. DAVENPORT
                                        Assistant Secretary
                                        Management and Administration


                  DERIVED AIR CONCENTRATIONS FOR CONTROLLING
                RADIATION EXPOSURE TO WORKERS AT DOE FACILITIES

The derived air concentrations (DAC) for limiting radiation exposures
through inhalation of radionuclides by workers are listed in Attachment 1,
page 4, Figure 1.  The values are based on either a stochastic (committed
effective dose equivalent) dose limit of 5 rem (0.05 Sv) or a nonstochastic
(organ) dose limit of 50 rem (0.5 Sv) per year, whichever is more limiting.
(Note:  the 15 rem [0.15 Sv] dose limit for the lens of the eye does not
appear as a critical organ dose limit.)

Table 1 contains five columns of information:  (1) radionuclide; (2) inhaled
air DAC for lung retention class D (microCi/mL); (3) inhaled air DAC for
lung retention class W (microCi/mL); (4) inhaled air DAC for lung retention
class Y (microCi/mL); and (5) an indication of whether or not the DAC for
each class is controlled by the stochastic (effective dose equivalent) or
nonstochastic (tissue) dose.  The classes D, W, and Y have been established
by the International Commission on Radiological Protection (ICRP) to
describe the clearance of inhaled radionuclides from the lung.  This
classification refers to the approximate length of retention in the
pulmonary region.  Thus, the range of half-times is less than 10 days for
class D (days), from 10 to 100 days for class W (weeks), and greater than
100 days for class Y (years).  The DACs in Table 1 are listed by
radionuclide, in order of increasing atomic mass, and are based on the
assumption that the particle size distribution of the inhaled material is
unknown.  For this situation, the ICRP recommends that an assumed particle
size distribution of 1 micro m be used.  For situations where the particle
size distribution is known to differ significantly from 1 micro m,
appropriate corrections (as described in the DOE report Internal Dose
Conversion Factors for Calculation of Dose to the Public) 1/ can be made to
both the estimated dose to workers and the DACs.

Alternative absorption factors and lung retention classes for specific
compounds are listed by element in Table 2 for cross-referencing with the
inhalation DACs in Table 1.  The data shown in Figure 2 are listed by
element in alphabetical order.

The following assumptions and procedures were used in calculating these DAC
values for inhalation by workers:

(1)  The worker is assumed to inhale 2,400 m/3 of air during a 2000-hour
     work year, as defined by the ICRP in its Publication No. 23. 2/

____________________
1/   U.S. Department of Energy (DOE).  1988.  Internal Dose Conversion
     Factors for Calculation of Dose to the Public.  Washington, D.C.

2/   International Commission on Radiological Protection (ICRP).  1975.
     ICRP Publication 23:  Report of the Task Group on Reference Man.
     Pergamon Press, New York, New York.


(2)  The internal dose factors used in calculating the DAC values
     were taken from the report Internal Dose Conversion Factors for
     Calculation of Dose to the Public. 1/  These factors are based on the
     metabolic data and dosimetry models recommended by the ICRP in its
     Publication No. 30. 3/

The air immersion DAC values shown in Table 3 are based on a stochastic
limit of 5 rem (0.05 Sv) per year or a nonstochastic (organ) dose limit of
50 rem (0.5 Sv) per year.  Figure 3 contains three columns of information:
(1) radionuclide; (2) half-life in units of seconds (s), minutes (min),
hours (h), days (d), or years (y); and (3) air immersion DAC (micro Ci/mL).
The data in Table 3 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 atmospheric cloud.  The dose
conversion factors used to calculate the DAC values for air immersion were
taken from the DOE report External Dose-Rate Conversion Factors for
Calculation of Dose to the Public. 4/  The DAC value for air immersion
listed in Table 3 for a given radionuclide is determined either by a limit
on annual effective dose equivalent, which provides a limit on stochastic
radiation effects, or by a limit on annual dose equivalent to any organ,
which provides a limit on nonstochastic radiation effects.  For most of the
radionuclides listed in Table 3, the DAC value is determined by the limit on
annual effective dose equivalent.  Thus, the few cases where the DAC value
is determined by the limit on annual dose equivalent to skin are indicated
in the figure by an appropriate footnote.  Again, the DACs listed in Figure
3 account only for immersion in a semi-infinite cloud and do not account for
inhalation or ingestion exposures.  Three classes of radionuclides are
included in the air immersion DACs given in Figure 3, as described below.

(1)  Class 1.  The first class of radionuclides includes selected noble
     gases and short-lived activation products that occur in gaseous form.
     For these radionuclides, inhalation doses are negligible compared to
     the external dose from immersion in an atmospheric cloud.

(2)  Class 2.  The second class of radionuclides includes those for which a
     DAC value for inhalation has been calculated (using the ICRP inhalation
     dose equivalent factors), but for which the DAC value for external
     exposure to a contaminated atmospheric cloud is more restrictive (i.e.,
     results in a lower DAC value).  These radionuclides generally have
     half-lives of a few hours or less, or are eliminated from the body
     following inhalation sufficiently rapidly to limit the inhalation dose.

____________________
3/   International Commission on Radiological Protection (ICRP).  1979-1982.
     ICRP Publication 30:  Limits for Intakes of Radionuclides by Workers.
     Parts 1 to 3 and Supplements 2(3/4) through 8(4), Pergamon Press, New
     York, New York.

4/   U.S. Department of Energy (DOE).  1988.  External Dose-Rate Conversion
     Factors for Calculation of Dose to the Public.  Washington, D.C.


(3)  Class 3.  The third class of radionuclides includes selected isotopes
     with relatively short half-lives that were not considered in ICRP
     Publication 30.  These radionuclides typically have half-lives that are
     less than 10 minutes, they do not occur as a decay product of a
     longer-lived radionuclide, or they lack sufficient decay data to permit
     internal dose calculations.  These radionuclides are also typified by a
     radioactive emission of highly intense, high-energy photons and rapid
     removal from the body following inhalation.

The DAC values are given for individual radionuclides.  For known mixtures
of radionuclides, the sum of the ratio of the observed concentration of a
particular radionuclide and its corresponding DAC for all radionuclides in
the mixture must not exceed 1.0.


                                Table 1

Derived Air Concentrations (DAC) for Controlling Radiation Exposures to
Workers at DOE Facilities

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D / W / Y)
---------------         ------------ ------------ ------------   -----------
H-3 (Water) 2/             2.E-05        2.E-05      2.E-05       St/St/St
H-3 (Elemental) 2/         5.E-01        5.E-01      5.E-01       St/St/St

Be-7                         - 3/        9.E-06      8.E-06         /St/St
Be-10                        -           6.E-08      6.E-09         /St/St

C-11 (Org) 2/              2.E-04        2.E-04      2.E-04       St/St/St
C-11 (CO) 2/               5.E-04        5.E-04      5.E-04       St/St/St
C-11 (CO2) 2/              3.E-04        3.E-04      3.E-04       St/St/St
C-14 (Org) 2/              1.E-06        1.E-06      1.E-06       St/St/St
C-14 (CO) 2/               7.E-04        7.E-04      7.E-04       St/St/St
C-14 (CO2) 2/              9.E-05        9.E-05      9.E-05       St/St/St

F-18                       3.E-05        4.E-05      3.E-05       St/St/St

Na-22                      3.E-07          -           -          St/  /
Na-24                      2.E-06          -           -          St/  /

Mg-28                      7.E-07        5.E-07        -          St/St/

Al-26                      3.E-08        3.E-08        -          St/St/

Si-31                      1.E-05        1.E-05      1.E-05       St/St/St
Si-32                      1.E-07        5.E-08      2.E-09       St/St/St

P-32                       4.E-07        2.E-07        -          St/St/
P-33                       3.E-06        1.E-06        -          St/St/

S-35                       7.E-06        9.E-07        -          St/St/
S-35 (Gas)                               6.E-06        -            /St/

Cl-36                      1.E-06        J.E-07        -          St/St/
Cl-38                      2.E-05        2.E-05        -          St/St/
Cl-39                      2.E-05        2.E-05        -          St/St/

K-40                       2.E-07          -           -          St/  /
K-42                       2.E-06          -           -          St/  /
K-43                       4.E-06          -           -          St/  /
K-44                       3.E-05          -           -          St/  /
K-45                       5.E-05          -           -          St/  /

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D / W / Y)
---------------         ------------ ------------ ------------   -----------
Ca-41                        -           2.E-06        -            /E /
Ca-45                        -           3.E-07        -            /St/
Ca-47                        -           4.E-07        -            /St/

Sc-43                        -             -         1.E-05         /  /St
Sc-44m                       -             -         3.E-07         /  /St
Sc-44                        -             -         5.E-06         /  /St
Sc-46                        -             -         1.E-07         /  /St
Sc-47                        -             -         1.E-06         /  /St
Sc-48                        -             -         6.E-07         /  /St
Sc-49                        -             -         2.E-05         /  /St

Ti-44                      5.E-09        1.E-08      2.E-09       St/St/St
Ti-45                      1.E-05        1.E-05      1.E-05       St/St/St

V-47                       4.E-05        4.E-05        -          St/St/
V-48                       4.E-07        3.E-07        -          St/St/
V-49                       1.E-05        7.E-06        -          BS/St/

Cr-48                      5.E-06        3.E-06      3.E-06       St/St/St
Cr-49                      3.E-05        4.E-05      4.E-05       St/St/St
Cr-51                      2.E-05        1.E-05      8.E-06       St/St/St

Mn-51                      2.E-05        2.E-05        -          St/St/
Mn-52m                     4.E-05        4.E-05        -          St/St/
Mn-52                      5.E-07        4.E-07        -          St/St/
Mn-53                      5.E-06        5.E-06        -          BS/St/
Mn-54                      4.E-07        3.E-07        -          St/St/
Mn-56                      6.E-06        9.E-06        -          St/St/

Fe-52                      1.E-06        1.E-06        -          St/St/
Fe-55                      8.E-07        2.E-06        -          St/St/
Fe-59                      1.E-07        2.E-07        -          St/St/
Fe-60                      3.E-09        8.E-09        -          St/St/

Co-55                        -           1.E-06      1.E-06         /St/St
Co-56                        -           1.E-07      8.E-08         /St/St
Co-57                        -           1.E-06      3.E-07         /St/St
Co-58m                       -           4.E-05      3.E-05         /St/St
Co-58                        -           5.E-07      3.E-07         /St/St
Co-60m                       -           2.E-03      1.E-03         /St/St
Co-60                        -           7.E-08      1.E-08         /St/St
Co-61                        -           3.E-05      2.E-05         /St/St
Co-62m                       -           7.E-05      7.E-05         /St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Ni-56 (Inorg)              8.E-07        5.E-07        -          St/St/
Ni-56 (Vapor)                -           5.E-07        -            /St/
Ni-57 (Inorg)              2.E-06        1.E-06        -          St/St/
Ni-57 (Vapor)                -           3.E-06        -            /St/
Ni-59 (Inorg)              2.E-06        3.E-06        -          St/St/
Ni-59 (Vapor)                -           8.E-07        -            /St/
Ni-63 (Inorg)              7.E-07        1.E-06        -          St/St/
Ni-63 (Vapor)                -           3.E-07        -            /St/
Nl-65 (Inorg)              1.E-05        1.E-05        -          St/St/
Ni-65 (Vapor)                -           7.E-06        -            /St/
Ni-66 (Inorg)              7.E-07        3.E-07        -          St/St/
Ni-66 (Vapor)                -           1.E-06        -            /St/

Cu-60                      4.E-05        5.E-05      4.E-05       St/St/St
Cu-61                      1.E-05        2.E-05      1.E-05       St/St/St
Cu-64                      1.E-05        1.E-05      9.E-06       St/St/St
Cu-67                      3.E-06        2.E-06      2.E-06       St/St/St

Zn-62                        -             -         1.E-06         /  /St
Zn-63                        -             -         3.E-05         /  /St
Zn-65                        -             -         1.E-07         /  /St
Zn-69m                       -             -         3.E-06         /  /St
Zn-69                        -             -         6.E-05         /  /St
Zn-71m                       -             -         7.E-06         /  /St
Zn-72                        -             -         5.E-07         /  /St

Ga-65                      7.E-05        8.E-05        -          St/St/
Ga-66                      1.E-06        1.E-06        -          St/St/
Ga-67                      6.E-06        4.E-06        -          St/St/
Ga-68                      2.E-05        2.E-05        -          St/St/
Ga-70                      7.E-05        8.E-05        -          St/St/
Ga-72                      2.E-06        1.E-06        -          St/St/
Ga-73                      6.E-06        6.E-06        -          St/St/

Ge-66                      1.E-05        8.E-06        -          St/St/
Ge-67                      4.E-05        4.E-05        -          St/St/
Ge-68                      2.E-06        4.E-08        -          St/St/
Ge-69                      6.E-06        3.E-06        -          St/St/
Ge-71                      2.E-04        2.E-05        -          St/St/
Ge-75                      3.E-05        3.E-05        -          St/St/
Ge-77                      4.E-06        2.E-06        -          St/St/
Ge-78                      9.E-06        9.E-06        -          St/St/

As-69                        -           5.E-05        -            /St/

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
As-70                        -           2.E-05        -            /St/
As-71                        -           2.E-06        -            /St/
As-72                        -           6.E-07        -            /St/
As-73                        -           7.E-07        -            /St/
As-74                        -           3.E-07        -            /St/
As-76                        -           6.E-07        -            /St/
As-77                        -           2.E-06        -            /St/
As-78                        -           9.E-06        -            /St/

Se-70                      1.E-05        2.E-05        -          St/St/
Se-73m                     6.E-05        6.E-05        -          St/St/
Se-73                      6.E-06        7.E-06        -          St/St/
Se-75                      3.E-07        3.E-07        -          St/St/
Se-79                      3.E-07        2.E-07        -          St/St/
Se-81m                     3.E-05        3.E-05        -          St/St/
Se-81                      9.E-05        1.E-04        -          St/St/
Se-83                      5.E-05        5.E-05        -          St/St/

Br-74m                     1.E-05        2.E-05        -          St/St/
Br-74                      3.E-05        3.E-05        -          St/St/
Br-75                      2.E-05        2.E-05        -          St/St/
Br-76                      2.E-06        2.E-06        -          St/St/
Br-77                      1.E-05        8.E-06        -          St/St/
Br-80m                     7.E-06        6.E-06        -          St/St/
Sr-80                      8.E-05        9.E-05        -          St/St/
Br-82                      2.E-06        2.E-06        -          St/St/
Br-83                      3.E-05        3.E-05        -          St/St/
Br-84                      2.E-05        3.E-05        -          St/St/

Rb-79                      5.E-05          -           -          St/  /
Rb-81m                     1.E-04          -           -          St/  /
Rb-81                      2.E-05          -           -          St/  /
Rb-82m                     7.E-06          -           -          St/  /
Rb-83                      4.E-07          -           -          St/  /
Rb-84                      3.E-07          -           -          St/  /
Rb-86                      3.E-07          -           -          St/  /
Rb-87                      6.E-07          -           -          St/  /
Rb-88                      3.E-05          -           -          St/  /
Rb-89                      6.E-05          -           -          St/  /

Sr-80                      5.E-06          -         5.E-06       St/  /St
Sr-81                      3.E-05          -         3.E-05       St/  /St
Sr-83                      3.E-06          -         2.E-06       St/  /St
Sr-85m                     3.E-04          -         3.E-04       St/  /St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Sr-85                      1.E-06          -         7.E-07       St/  /St
Sr-87m                     5.E-05          -         6.E-05       St/  /St
Sr-89                      3.E-07          -         6.E-08       St/  /St
Sr-90                      8.E-09          -         2.E-09       St/  /St
Sr-91                      2.E-06          -         1.E-06       St/  /St
Sr-92                      4.E-06          -         3.E-06       St/  /St

Y-86m                        -           2.E-05      2.E-05         /St/St
Y-86                         -           1.E-06      1.E-06         /St/St
Y-87                         -           1.E-06      1.E-06         /St/St
Y-88                         -           1.E-07      1.E-07         /St/St
Y-90m                        -           5.E-06      5.E-06         /St/St
Y-90                         -           3.E-07      3.E-07         /St/St
Y-91m                        -           1.E-04      7.E-05         /St/St
Y-91                         -           7.E-08      5.E-08         /St/St
Y-92                         -           3.E-06      3.E-06         /St/St
Y-93                         -           1.E-06      1.E-06         /St/St
Y-94                         -           3.E-05      3.E-05         /St/St
Y-95                         -           6.E-05      6.E-05         /St/St

Zr-86                      2.E-06        1.E-06      1.E-06       St/St/St
Zr-88                      9.E-08        2.E-07      1.E-07       St/St/St
Zr-89                      2.E-06        1.E-06      1.E-06       St/St/St
Zr-93                      3.E-09        1.E-08      2.E-08       BS/BS/BS
Zr-95                      6.E-08        2.E-07      1.E-07       BS/St/St
Zr-97                      8.E-07        6.E-07      5.E-07       St/St/St

Nb-88                        -           1.E-04      9.E-05         /St/St
Nb-89 (66 min)               -           2.E-05      2.E-05         /St/St
Nb-89 (122 min)              -           8.E-06      7.E-06         /St/St
Nb-90                        -           1.E-06      1.E-06         /St/St
Nb-93m                       -           5.E-07      7.E-08         /St/St
Nb-94                        -           8.E-08      6.E-09         /St/St
Nb-95m                       -           1.E-06      9.E-07         /St/St
Nb-95                        -           5.E-07      5.E-07         /St/St
Nb-96                        -           1.E-06      1.E-06         /St/St
Nb-97                        -           3.E-05      3.E-05         /St/St
Nb-98                        -           2.E-05      2.E-05         /St/St

Mo-90                      3.E-06          -         2.E-06       St/  /St
Mo-93m                     7.E-06          -         6.E-06       St/  /St
Mo-93                      2.E-06          -         7.E-08       St/  /St
Mo-99                      1.E-06          -         6.E-07       St/  /St
Mo-101                     6.E-05          -         6.E-05       St/  /St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Tc-93m                     7.E-05        1.E-04        -          St/St/
Tc-93                      3.E-05        4.E-05        -          St/St/
Tc-94m                     2.E-05        2.E-05        -          St/St/
Tc-94                      8.E-06        1.E-05        -          St/St/
Tc-96m                     1.E-04        1.E-04        -          St/St/
Tc-96                      1.E-06        9.E-07        -          St/St/
Tc-97m                     3.E-06        5.E-07        -          SW/St/
Tc-97                      2.E-05        2.E-06        -          St/St/
Tc-98                      7.E-07        1.E-07        -          St/St/
Tc-99m                     6.E-05        1.E-04        -          St/St/
Tc-99                      2.E-06        3.E-07        -          SW/St/
Tc-101                     1.E-04        2.E-04        -          St/St/
Tc-104                     3.E-05        4.E-05        -          St/St/

Ru-94                      2.E-05        3.E-05      2.E-05       St/St/St
Ru-97                      8.E-06        5.E-06      5.E-06       St/St/St
Ru-103                     7.E-07        4.E-07      3.E-07       St/St/St
Ru-105                     6.E-06        6.E-06      5.E-06       St/St/St
Ru-106                     4.E-08        2.E-08      5.E-09       St/St/St

Rh-99m                     2.E-05        3.E-05      3.E-05       St/St/St
Rh-99                      1.E-06        9.E-07      8.E-07       St/St/St
Rh-100                     2.E-06        2.E-06      2.E-06       St/St/St
Rh-101m                    5.E-06        3.E-06      3.E-06       St/St/St
Rh-101                     2.E-07        3.E-07      7.E-08       St/St/St
Rh-102m                    2.E-07        2.E-07      5.E-08       St/St/St
Rh-102                     4.E-08        7.E-08      2.E-08       St/St/St
Rh-103m                    4.E-04        5.E-04      5.E-04       St/St/St
Rh-105                     5.E-06        3.E-06      2.E-06       St/St/St
Rh-106m                    1.E-05        1.E-05      1.E-05       St/St/St
Rh-107                     1.E-04        1.E-04      1.E-04       St/St/St

Pd-100                     6.E-07        5.E-07      6.E-07       St/St/St
Pd-101                     1.E-05        1.E-05      1.E-05       St/St/St
Pd-103                     3.E-06        2.E-06      1.E-06       St/St/St
Pd-107                     9.E-06        3.E-06      2.E-07       K /St/St
Pd-109                     3.E-06        2.E-06      2.E-06       St/St/St

Ag-102                     8.E-05        9.E-05      8.E-05       St/St/St
Ag-103                     4.E-05        6.E-05      5.E-05       St/St/St
Ag-104m                    4.E-05        5.E-05      5.E-05       St/St/St
Ag-104                     3.E-05        6.E-05      6.E-05       St/St/St
Ag-105                     4.E-07        7.E-07      7.E-07       St/St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Ag-106m                    3.E-07         4.E-07     4.E-07       St/St/St
Ag-106                     7.E-07         9.E-05     8.E-05       St/St/St
Ag-108m                    8.E-08         1.E-07     1.E-08       St/St/St
Ag-110m                    6.E-08         8.E-08     4.E-08       St/St/St
Ag-111                     7.E-07         4.E-07     4.E-07       L /St/St
Ag-112                     3.E-06         4.E-06     4.E-06       St/St/St
Ag-115                     4.E-05         4.E-05     3.E-05       St/St/St

Cd-104                     3.E-05         5.E-05     5.E-05       St/St/St
Cd-107                     2.E-05         2.E-05     2.E-05       St/St/St
Cd-109                     1.E-08         5.E-08     5.E-08       K /K /St
Cd-113m                    1.E-08         4.E-09     5.E-09       K /K /St
Cd-113                     9.E-07         3.E-09     6.E-09       K /K /St
Cd-115m                    2.E-06         5.E-08     6.E-08       K /St/St
Cd-115                     6.E-05         5.E-07     6.E-07       St/St/St
Cd-117m                    5.E-06         7.E-06     6.E-06       St/St/St
Cd-117                     5.E-06         7.E-06     6.E-06       St/St/St

In-109                     2.E-05         3.E-05       -          St/St/
In-110 (69 min)            2.E-05         2.E-05       -          St/St/
In-110 (5 h)               7.E-06         8.E-06       -          St/St/
In-111                     3.E-06         3.E-06       -          St/St/
In-112                     3.E-04         3.E-04       -          St/St/
In-113m                    6.E-05         8.E-05       -          St/St/
In-114m                    3.E-08         4.E-08       -          St/St/
In-115m                    2.E-05         2.E-05       -          St/St/
In-115                     6.E-10         2.E-09       -          St/St/
In-116m                    3.E-05         5.E-05       -          St/St/
In-117m                    1.E-05         2.E-05       -          St/St/
In-117                     7.E-05         9.E-05       -          St/St/
In-119m                    5.E-05         6.E-05       -          St/St/

Sn-110                     5.E-06         5.E-06       -          St/St/
Sn-111                     9.E-05         2.E-04       -          St/St/
Sn-113                     5.E-07         2.E-07       -          St/St/
Sn-117m                    5.E-07         6.E-07       -          BS/St/
Sn-119m                    1.E-06         4.E-07       -          St/St/
Sn-121m                    4.E-07         2.E-07       -          St/St/
Sn-121                     6.E-06         5.E-06       -          St/St/
Sn-123m                    5.E-05         6.E-05       -          St/St/
Sn-123                     3.E-07         7.E-08       -          St/St/
Sn-125                     4.E-07         2.E-07       -          St/St/
Sn-126                     2.E-08         3.E-08       -          St/St/
Sn-127                     8.E-06         8.E-06       -          St/St/

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Sn-128                     1.E-05        1.E-05        -          St/St/

Sb-115                     1.E-04        1.E-04        -          St/St/
Sb-116m                    3.E-05        6.E-05        -          St/St/
Sb-116                     1.E-04        1.E-04        -          St/St/
Sb-117                     9.E-05        1.E-04        -          St/St/
Sb-118m                    8.E-06        9.E-06        -          St/St/
Sb-119                     2.E-05        1.E-05        -          St/St/
Sb-120 (16 min)            2.E-04        2.E-04        -          St/St/
Sb-120 (6 d)               9.E-07        6.E-07        -          St/St/
Sb-122                     1.E-06        4.E-07        -          St/St/
Sb-124m                    3.E-04        3.E-04        -          St/St/
Sb-124                     4.E-07        1.E-07        -          St/St/
Sb-125                     1.E-06        2.E-07        -          St/St/
Sb-126m                    8.E-05        8.E-05        -          St/St/
Sb-126                     4.E-07        2.E-07        -          St/St/
Sb-127                     9.E-07        4.E-07        -          St/St/
Sb-128 (9 h)               2.E-06        1.E-06        -          St/St/
Sb-126 (10 min)            2.E-04        2.E-04        -          St/St/
Sb-129                     4.E-06        4.E-06        -          St/St/
Sb-130                     3.E-05        3.E-05        -          St/St/
Sb-13I                     1.E-05        1.E-05        -          T /T /

Te-116                     9.E-06        1.E-05        -          St/St/
Te-121m                    8.E-08        2.E-07        -          BS/St/
Te-121                     2.E-06        1.E-06        -          St/St/
Te-123m                    9.E-08        2.E-07        -          BS/St/
Te-123                     8.E-08        2.E-07        -          BS/05/
Te-125m                    2.E-07        3.E-07        -          BS/St/
Te-127m                    1.E-07        1.E-07        -          BS/St/
Te-127                     9.E-06        7.E-06        -          St/St/
Te-129m                    3.E-07        1.E-07        -          St/St/
Te-129                     3.E-05        3.E-05        -          St/St/
Te-131m                    2.E-07        2.E-07        -          T /T /
Te-131                     2.E-06        2.E-06        -          T /T /
Te-132                     9.E-08        9.E-08        -          T /T /
Te-133m                    2.E-06        2.E-06        -          T /T /
Te-133                     9.E-06        9.E-06        -          T /T /
Te-134                     1.E-05        1.E-05        -          T /T /

I-120m                     9.E-06          -           -          St/  /
I-120                      4.E-06          -           -          T /  /
I-121                      7.E-06          -           -          T /  /
I-123                      3.E-06          -           -          T /  /

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
I-124                      3.E-08          -           -          T /  /
I-125                      3.E-08          -           -          T /  /
I-126                      1.E-08          -           -          T /  /
I-128                      5.E-05          -           -          St/  /
I-129                      4.E-09          -           -          T /  /
I-130                      3.E-07          -           -          T /  /
I-131                      2.E-08          -           -          T /  /
I-132m                     4.E-06          -           -          T /  /
I-132                      3.E-06          -           -          T /  /
I-133                      1.E-07          -           -          T /  /
I-134                      2.E-05          -           -          E /  /
I-135                      7.E-07          -           -          T /  /

Cs-125                     6.E-05          -           -          St/  /
Cs-127                     4.E-05          -           -          St/  /
Cs-129                     1.E-05          -           -          St/  /
Cs-130                     8.E-05          -           -          St/  /
Cs-131                     1.E-05          -           -          St/  /
Cs-132                     2.E-06          -           -          St/  /
Cs-134m                    6.E-05          -           -          St/  /
Cs-134                     4.E-08          -           -          St/  /
Cs-135m                    8.E-05          -           -          St/  /
Cs-135                     5.E-07          -           -          St/  /
Cs-136                     3.E-07          -           -          St/  /
Cs-137                     7.E-08          -           -          St/  /
Cs-138                     2.E-05          -           -          St/  /

Ba-126                     6.E-06          -           -          St/  /
Ba-128                     7.E-07          -           -          St/  /
Ba-131m                    6.E-04          -           -          St/  /
Ba-131                     3.E-06          -           -          St/  /
Ba-133m                    4.E-06          -           -          St/  /
Ba-133                     3.E-07          -           -          St/  /
Ba-135m                    5.E-06          -           -          St/  /
Ba-139                     1.E-05          -           -          St/  /
Ba-140                     6.E-07          -           -          St/  /
Ba-141                     3.E-05          -           -          St/  /
Ba-142                     6.E-05          -           -          St/  /

La-131                     5.E-05        7.E-05        -          St/St/
La-132                     4.E-06        5.E-06        -          St/St/
La-135                     4.E-05        4.E-05        -          St/St/
La-137                     3.E-08        1.E-07        -          L /E /
La-138                     2.E-09        6.E-09        -          St/St/

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
La-140                     6.E-07        5.E-07        -          St/St/
La-141                     4.E-06        5.E-06        -          St/St/
La-142                     9.E-06        1.E-05        -          St/St/
La-143                     4.E-05        4.E-05        -          St/St/

Ce-134                       -           3.E-07      3.E-07         /St/St
Ce-135                       -           2.E-06      2.E-06         /St/St
Ce-137m                      -           2.E-06      2.E-06         /St/St
Ce-137                       -           6.E-05      5.E-05         /St/St
Ce-139                       -           3.E-07      3.E-07         /St/St
Ce-141                       -           3.E-07      3.E-07         /St/St
Ce-143                       -           8.E-07      7.E-07         /St/St
Ce-144                       -           1.E-06      6.E-09         /St/St

Pr-136                       -           1.E-04      9.E-05         /St/St
Pr-137                       -           6.E-05      6.E-05         /St/St
Pr-138m                      -           2.E-05      2.E-05         /St/St
Pr-139                       -           5.E-05      5.E-05         /St/St
Pr-142m                      -           7.E-05      6.E-05         /St/St
Pr-142                       -           8.E-07      8.E-07         /St/St
Pr-143                       -           3.E-07      3.E-07         /St/St
Pr-144                       -           5.E-05      5.E-05         /St/St
Pr-145                       -           4.E-06      3.E-06         /St/St
Pr-147                       -           8.E-05      8.E-05         /St/St

Nd-136                       -           2.E-05      2.E-05         /St/St
Nd-138                       -           3.E-06      2.E-06         /St/St
Nd-139m                      -           7.E-06      6.E-06         /St/St
Nd-139                       -           1.E-04      1.E-04         /St/St
Nd-141                       -           3.E-04      3 E-04         /St/St
Nd-147                       -           4.E-07      3.E-07         /St/St
Nd-149                       -           1.E-05      1.E-05         /St/St
Nd-151                       -           8.E-05      8.E-05         /St/St

Pm-141                       -           8.E-05      7.E-05         /St/St
Pm-143                       -           3.E-07      3.E-07         /St/St
Pm-144                       -           5.E-08      5.E-08         /St/St
Pm-145                       -           7.E-08      8.E-08         /BS/St
Pm-146                       -           2.E-08      2.E-08         /St/St
Pm-147                       -           6.E-08      6.E-08         /BS/St
Pm-148m                      -           1.E-07      1.E-07         /St/St
Pm-148                       -           2.E-07      2.E-07         /St/St
Pm-149                       -           8.E-07      8.E-07         /St/St
Pm-150                       -           8.E-06      7.E-06         /St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Pm-151                       -           2.E-06      1.E-06         /St/St

Sm-141m                      -           4.E-05        -            /St/
Sm-141                       -           7.E-05        -            /St/
Sm-142                       -           1.E-05        -            /St/
Sm-145                       -           2.E-07        -            /St/
Sm-146                       -           1.E-11        -            /BS/
Sm-147                       -           2.E-11        -            /BS/
Sm-151                       -           4.E-08        -            /BS/
Sm-153                       -           1.E-06        -            /St/
Sm-155                       -           9.E-05        -            /St/
Sm-156                       -           4.E-06        -            /St/

Eu-145                       -           8.E-07        -            /St/
Eu-146                       -           5.E-07        -            /St/
Eu-147                       -           7.E-07        -            /St/
Eu-148                       -           2.E-07        -            /St/
Eu-149                       -           1.E-06        -            /St/
Eu-150 (12 h)                -           3.E-06        -            /St/
Eu-150 (34 yr)               -           8.E-09        -            /St/
Eu-152m                      -           3.E-06        -            /St/
Eu-152                       -           1.E-08        -            /St/
Eu-154                       -           8.E-09        -            /St/
Eu-155                       -           4.E-08        -            /BS/
Eu-156                       -           2.E-07        -            /St/
Eu-157                       -           2.E-06        -            /St/
Eu-158                       -           2.E-05        -            /St/

Gd-145                     7.E-05        7.E-05        -          St/St/
Gd-146                     5.E-08        1.E-07        -          St/St/
Gd-147                     2.E-06        2.E-06        -          St/St/
Gd-148                     3.E-12        1.E-11        -          BS/BS/
Gd-149                     9.E-07        1.E-06        -          St/St/
Gd-151                     2.E-07        5.E-07        -          BS/St/
Gd-152                     4.E-12        2.E-11        -          BS/BS/
Gd-153                     6.E-08        3.E-07        -          BS/St/
Gd-159                     3.E-06        2.E-06        -          St/St/

Tb-147                       -           1.E-05        -            /St/
Tb-149                       -           3.E-07        -            /St/
Tb-150                       -           9.E-06        -            /St/
Tb-151                       -           4.E-06        -            /St/
Tb-153                       -           3.E-06        -            /St/
Tb-154                       -           2.E-06        -            /St/

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Tb-155                       -           3.E-06        -            /St/
Tb-156m (24 h)               -           3.E-06        -            /St/
Tb-156m (5 h)                -           1.E-05        -            /St/
Tb-156                       -           6.E-07        -            /St/
Tb-157                       -           1.E-07        -            /BS/
Tb-158                       -           8.E-09        -            /St/
Tb-160                       -           1.E-07        -            /St/
Tb-161                       -           7.E-07        -            /St/

Dy-155                       -           1.E-05        -            /St/
Dy-157                       -           3.E-05        -            /St/
Dy-159                       -           1.E-06        -            /St/
Dy-165                       -           2.E-05        -            /St/
Dy-166                       -           3.E-07        -            /St/

Ho-155                       -           7.E-05        -            /St/
Ho-157                       -           6.E-04        -            /St/
Ho-159                       -           4.E-04        -            /St/
Ho-161                       -           2.E-04        -            /St/
Ho-162m                      -           1.E-04        -            /St/
Ho-162                       -           1.E-03        -            /St/
Ho-164m                      -           1.E-04        -            /St/
Ho-164                       -           3.E-04        -            /St/
Ho-166m                      -           3.E-09        -            /St/
Ho-166                       -           7.E-07        -            /St/
Ho-167                       -           2.E-05        -            /St/

Er-161                       -           3.E-05        -            /St/
Er-165                       -           8.E-05        -            /St/
Er-169                       -           1.E-06        -            /St/
Er-171                       -           4.E-06        -            /St/
Er-172                       -           6.E-07        -            /St/

Tm-162                       -           1.E-04        -            /St/
Tm-166                       -           6.E-06        -            /St/
Tm-167                       -           8.E-07        -            /St/
Tm-170                       -           9.E-08        -            /St/
Tm-171                       -           1.E-07        -            /BS/
Tm-172                       -           5.E-07        -            /St/
Tm-173                       -           5.E-06        -            /St/
Tm-175                       -           1.E-04        -            /St/

Yb-162                       -           1.E-04      1.E-04         /St/St
Yb-166                       -           8.E-07      8.E-07         /St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Yb-167                       -           3.E-04      3.E-04         /St/St
Yb-169                       -           3.E-07      3.E-07         /St/St
Yb-175                       -           1.E-06      1.E-06         /St/St
Yb-177                       -           2.E-05      2.E-05         /St/St
Yb-178                       -           2.E-05      1.E-05         /St/St

Lu-169                       -           2.E-06      2.E-06         /St/St
Lu-170                       -           9.E-07      8.E-07         /St/St
Lu-171                       -           8.E-07      8.E-07         /St/St
Lu-172                       -           5.E-07      5.E-07         /St/St
Lu-173                       -           1.E-07      1.E-07         /BS/St
Lu-174m                      -           1.E-07      9.E-08         /BS/St
Lu-174                       -           5.E-08      7.E-08         /BS/St
Lu-176m                      -           1.E-05      1.E-05         /St/St
Lu-176                       -           2.E-09      3.E-O9         /BS/St
Lu-177m                      -           5.E-08      3.E-08         /BS/St
Lu-177                       -           9.E-07      9.E-07         /St/St
Lu-178m                      -           8.E-05      7.E-05         /St/St
Lu-178                       -           5.E-05      5.E-05         /St/St
Lu-179                       -           8.E-06      6.E-06         /St/St

Hf-170                     2.E-06        2.E-06        -          St/St/
Hf-172                     4.E-09        2.E-08        -          BS/BS/
Hf-173                     5.E-06        5.E-06        -          St/St/
Hf-175                     4.E-07        5.E-07        -          BS/St/
Hf-177m                    2.E-05        4.E-05        -          St/St/
Hf-178m                    6.E-10        2.E-09        -          BS/BS/
Hf-179m                    1.E-07        3.E-07        -          BS/St/
Hf-180m                    9.E-06        1.E-05        -          St/St/
Hf-181                     7.E-08        2.E-07        -          BS/St/
Hf-182m                    4.E-05        6.E-05        -          St/St/
Hf-182                     3.E-10        1.E-09        -          BS/BS/
Hf-183                     2.E-05        2.E-05        -          St/St/
Hf-184                     3.E-06        3.E-06        -          St/St/

Ta-172                       -           5.E-05      4.E-05         /St/St
Ta-173                       -           8.E-06      7.E-06         /St/St
Ta-174                       -           4.E-05      4.E-05         /St/St
Ta-175                       -           7.E-06      6.E-06         /St/St
Ta-176                       -           5.E-06      5.E-06         /St/St
Ta-177                       -           8.E-06      7.E-06         /St/St
Ta-178                       -           4.E-05      3.E-05         /St/St
Ta-179                       -           2.E-06      4.E-07         /St/St
Ta-180m                      -           3.E-05      2.E-05         /St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Ta-180                       -           2.E-07      1.E-08         /St/St
Ta-182m                      -           2.E-04      2.E-04         /St/St
Ta-182                       -           1.E-07      6.E-08         /St/St
Ta-183                       -           5.E-07      4.E-07         /St/St
Ta-184                       -           2.E-06      2.E-06         /St/St
Ta-185                       -           3.E-05      3.E-05         /St/St
Ta-186                       -           1.E-04      9.E-05         /St/St

W-176                      2.E-05          -           -          St/  /
W-177                      4.E-05          -           -          St/  /
W-178                      8.E-06          -           -          St/  /
W-179                      7.E-04          -           -          St/  /
W-181                      1.E-05          -           -          St/  /
W-185                      3.E-06          -           -          St/  /
W-187                      4.E-06          -           -          St/  /
W-188                      5.E-07          -           -          St/  /

Re-177                     1.E-04        2.E-04        -          St/St/
Re-178                     1.E-04        1.E-04        -          St/St/
Re-181                     4.E-06        4.E-06        -          St/St/
Re-182 (64 h)              1.E-06        9.E-07        -          St/St/
Re-182 (12 h)              5.E-06        6.E-06        -          St/St/
Re-184m                    1.E-06        2.E-07        -          St/St/
Re-184                     2.E-06        6.E-07        -          St/St/
Re-186m                    7.E-07        6.E-08        -          SW/St/
Re-186                     1.E-06        7.E-07        -          St/St/
Re-187                     3.E-04        4.E-05        -          SW/St/
Re-188m                    6.E-05        6.E-05        -          St/St/
Re-188                     1.E-06        1.E-06        -          St/St/
Re-189                     2.E-06        2.E-06        -          St/St/

Os-180                     2.E-04        2.E-04      2.E-04       St/St/St
Os-181                     2.E-05        2.E-05      2.E-05       St/St/St
Os-182                     2.E-06        2.E-06      2.E-06       St/St/St
Os-185                     2.E-07        3.E-07      3.E-07       St/St/St
Os-189m                    1.E-04        9.E-05      7.E-05       St/St/St
Os-191m                    1.E-06        9.E-06      7.E-06       St/St/St
Os-191                     9.E-07        7.E-07      6.E-07       St/St/St
Os-193                     2.E-06        1.E-06      1.E-06       St/St/St
Os-194                     2.E-08        2.E-08      3.E-09       St/St/St

Ir-182                     6.E-05        6.E-05      5.E-05       St/St/St
Ir-184                     1.E-05        1.E-05      1.E-05       St/St/St
Ir-185                     5.E-06        5.E-06      4.E-06       St/St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Ir-186                     3.E-06        3.E-06      2.E-06       St/St/St
Ir-187                     1.E-05        1.E-05      1.E-05       St/St/St
Ir-188                     2.E-06        2.E-06      1.E-06       St/St/St
Ir-189                     2.E-06        2.E-06      2.E-06       St/St/St
Ir-190m                    8.E-05        9.E-05      8.E-05       St/St/St
Ir-190                     4.E-07        4.E-07      4.E-07       St/St/St
Ir-192m                    4.E-08        9.E-08      6.E-09       St/St/St
Ir-192                     1.E-07        2.E-07      9.E-08       St/St/St
Ir-194m                    4.E-08        7.E-08      4.E-08       St/St/St
Ir-194                     1.E-06        8.E-07      8.E-07       St/St/St
Ir-195m                    1.E-05        1.E-05      9.E-06       St/St/St
Ir-195                     2.E-05        2.E-05      2.E-05       St/St/St

Pt-186                     2.E-05          -           -          St/  /
Pt-188                     7.E-07          -           -          St/  /
Pt-189                     1.E-05          -           -          St/  /
Pt-191                     3.E-06          -           -          St/  /
Pt-193m                    2.E-06          -           -          St/  /
Pt-193                     1.E-05          -           -          St/  /
Pt-l95m                    2.E-06          -           -          St/  /
Pt-197m                    2.E-05          -           -          St/  /
Pt-197                     4.E-06          -           -          St/  /
Pt-199                     6.E-05          -           -          St/  /
Pt-200                     1.E-06          -           -          St/  /

Au-193                     1.E-05        8.E-06      8.E-06       St/St/St
Au-194                     3.E-06        2.E-06      2.E-06       St/St/St
Au-195                     5.E-06        6.E-07      2.E-07       St/St/St
Au-198m                    1.E-06        5.E-07      5.E-07       St/St/St
Au-198                     2.E-06        7.E-07      7.E-07       St/St/St
Au-199                     4.E-06        2.E-06      2.E-06       St/St/St
Au-200m                    1.E-06        1.E-06      1.E-06       St/St/St
Au-200                     3.E-05        3.E-05      3.E-05       St/St/St
Au-201                     9.E-05        1.E-04      9.E-05       St/St/St

Hg-193m (Org)              6.E-06          -           -          St/  /
Hg-193m (Inorg)            4.E-06        3.E-06        -          St/St/
Hg-193m (Vapor)              -           4.E-06        -            /St/
Hg-193 (Org)               3.E-05          -           -          St/  /
Hg-193 (Inorg)             2.E-05        2.E-05        -          St/St/
Hg-193 (Vapor)               -           1.E-05        -            /St/
Hg-194 (Org)               1.E-08          -           -          St/  /
Hg-194 (Inorg)             2.E-08        5.E-08        -          St/St/
Hg-194 (Vapor)               -           1.E-08        -            /St/

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Hg-195m (Org)              3.E-06          -           -          St/  /
Hg-195m (Inorg)            2.E-06        2.E-06        -          St/St/
Hg-195m (Vapor)              -           2.E-06        -            /St/
Hg-195 (Org)               2.E-05          -           -          St/
Hg-195 (Inorg)             1.E-05        1.E-05        -          St/St/
Hg-195 (Vapor)               -           1.E-05        -            /St/
Hg-197m (Org)              4.E-06          -           -          St/  /
Hg-197m (Inorg)            3.E-06        2.E-06        -          St/St/
Hg-197m (Vapor)              -           2.E-06        -            /St/
Hg-197 (Org)               6.E-06          -           -          St/  /
Hg-197 (Inorg)             5.E-06        4.E-06        -          St/St/
Hg-197 (Vapor)               -           3.E-05        -            /St/
Hg-199m (Org)              7.E-05          -           -          St/  /
Hg-199m (Inorg)            6.E-05        7.E-05        -          St/St/
Hg-199m (Vapor)              -           3.E-05        -            /St/
Hg-203 (Org)               3.E-07          -           -          St/  /
Hg-203 (Inorg)             5.E-07        5.E-07        -          St/St/
Hg-203 (Vapor)               -           3.E-07        -            /St/

Tl-194m                    6.E-05          -           -          St/  /
Tl-194                     3.E-04          -           -          St/  /
Tl-195                     5.E-05          -           -          St/  /
Tl-197                     5.E-05          -           -          St/  /
Tl-198m                    2.E-05          -           -          St/  /
Tl-198                     1.E-05          -           -          St/  /
Tl-199                     3.E-05          -           -          St/  /
Tl-200                     5.E-06          -           -          St/  /
Tl-201                     9.E-06          -           -          St/  /
Tl-202                     2.E-06          -           -          St/  /
Tl-204                     9.E-07          -           -          St/  /

Pb-195m                    8.E-05          -           -          St/  /
Pb-198                     3.E-05          -           -          St/  /
Pb-199                     3.E-05          -           -          St/  /
Pb-200                     3.E-06          -           -          St/  /
Pb-201                     9.E-06          -           -          St/  /
Pb-202m                    1.E-05          -           -          St/  /
Pb-202                     2.E-08          -           -          St/  /
Pb-203                     4.E-06          -           -          St/  /
Pb-205                     6.E-07          -           -          St/  /
Pb-209                     2.E-05          -           -          St/  /
Pb-210                     1.E-10          -           -          BS/  /
Pb-211                     3.E-07          -           -          St/  /
Pb-212                     1.E-08          -           -          St/  /

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Pb-214                     3.E-07          -           -          St/  /

Bi-200                     3.E-05        4.E-05        -          St/St/
Bi-201                     1.E-05        2.E-05        -          St/St/
Bi-202                     2.E-05        3.E-05        -          St/St/
Bi-203                     3.E-06        2.E-06        -          St/St/
Bi-205                     1.E-06        5.E-07        -          St/St/
Bi-206                     6.E-07        4.E-07        -          St/St/
Bi-207                     7.E-07        2.E-07        -          St/St/
Bi-210m                    2.E-09        3.E-10        -          K /St/
Bi-210                     1.E-07        1.E-08        -          K /St/
Bi-212                     1.E-07        1.E-07        -          St/St/
Bi-213                     1.E-07        2.E-07        -          St/St/
Bi-214                     3.E-07        4.E-07        -          St/St/

Po-203                     3.E-05        4.E-05        -          St/St/
Po-205                     2.E-05        3.E-05        -          St/St/
Po-207                     1.E-05        1.E-05        -          St/St/
Po-210                     3.E-10        3.E-10        -          E /St/

At-207                     1.E-06        9.E-07        -          St/St/
At-211                     3.E-08        2.E-08        -          St/St/

Rn-220                     8.E-09 4/       - 4/        - 4/          - 4/
Rn-222                     3.E-08 4/       - 4/        - 4/          - 4/

Fr-222                     2.E-07          -           -          St/  /
Fr-223                     3.E-07          -           -          St/  /

Ra-223                       -           3.E-10        -            /St/
Ra-224                       -           7.E-10        -            /St/
Ra-225                       -           3.E-10        -            /St/
Ra-226                       -           3.E-10        -            /St/
Ra-227                       -           6.E-06        -            /BS/
Ra-228                       -           5.E-10        -            /St/

Ac-224                     1.E-08        2.E-08      2.E-08       BS/St/St
Ac-225                     1.E-10        3.E-10      3.E-10       BS/St/St
Ac-226                     1.E-09        2.E-09      2.E-09       BS/St/St
Ac-227                     2.E-13        7.E-13      2.E-12       BS/BS/St
Ac-228                     4.E-09        2.E-08      2.E-08       BS/BS/St

Th-226                       -           7.E-08      6.E-08         /St/St
Th-227                       -           1.E-10      1.E-10         /St/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Th-228                       -           4.E-12      7.E-12         /BS/St
Th-229                       -           4.E-13      1.E-12         /BS/BS
Th-230                       -           3.E-12      7.E-12         /BS/BS
Th-231                       -           3.E-06      3.E-06         /St/St
Th-232                       -           5.E-13      1.E-12         /BS/BS
Th-234                       -           9.E-08      6.E-08         /St/St

Pa-227                       -           5.E-08      4.E-08         /St/St
Pa-228                       -           5.E-09      5.E-09         /BS/St
Pa-233                       -           2.E-09      1.E-09         /St/St
Pa-231                       -           7.E-13      2.E-12         /BS/BS
Pa-232                       -           9.E-09      2.E-08         /BS/BS
Pa-233                       -           3.E-07      2.E-07         /St/St
Pa-234                       -           3.E-06      3.E-06         /St/St

U-230                      2.E-10        1.E-10      1.E-10       BS/St/St
U-231                      3.E-06        2.E-06      2.E-06       St/St/St
U-232                      9.E-11        2.E-10      3.E-12       BS/St/St
U-233                      5.E-I0        3.E-10      2.E-11       BS/St/St
U-234                      5.E-10        3.E-10      2.E-11       BS/St/St
U-235                      6.E-10        3.E-10      2.E-11       BS/St/St
U-236                      6.E-10        3.E-10      2.E-11       BS/St/St
U-237                      1.E-06        7.E-07      6.E-07       St/St/St
U-238                      6.E-10        3.E-10      2.E-11       BS/St/St
U-239                      8.E-05        7.E-05      6.E-05       St/St/St
U-240                      2.E-06        1.E-06      1.E-06       St/St/St

Np-232                       -           1.E-06 5/     -            /BS/
Np-233                       -           1.E-03 5/     -            /St/
Np-234                       -           1.E-06 5/     -            /St/
Np-235                       -           5.E-07 5/     -            /BS/
Np-136 (1.E+05 yr)           -           1.E-11 5/     -            /BS/
Np-236 (22 h)                -           2.E-08 5/     -            /BS/
Np-237                       -           2.E-12 5/     -            /BS/
Np-238                       -           4.E-08 5/     -            /BS/
Np-239                       -           1.E-06 5/     -            /St/
Np-240                       -           3.E-05 5/     -            /St/

Pu-234                       -           9.E-08 5/   8.E-08 5/      /St/St
Pu-235                       -           1.E-03 5/   1.E-03 5/      /St/St
Pu-236                       -           7.E-12 5/   1.E-11 5/      /BS/St
Pu-237                       -           1.E-06 5/   1.E-06 5/      /St/St
Pu-238                       -           3.E-12 5/   7.E-12 5/      /BS/BS
Pu-239                       -           2.E-12 5/   6.E-12 5/      /BS/BS

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Pu-240                       -           2.E-12 5/   6.E-12 5/      /BS/BS
Pu-241                       -           1.E-10 5/   3.E-10 5/      /BS/BS
Pu-242                       -           2.E-12 5/   6.E-12 5/      /BS/BS
Pu-243                       -           1.E-05 5/   1.E-05 5/      /St/St
Pu-244                       -           2.E-12 5/   6.E-12 5/      /BS/BS
Pu-245                       -           2.E-06 5/   2.E-06 5/      /St/St

Am-237                       -           1.E-04 5/     -            /St/
Am-238                       -           1.E-06 5/     -            /BS/
Am-239                       -           5.E-06 5/     -            /St/
Am-240                       -           1.E-06 5/     -            /St/
Am-241                       -           2.E-12 5/     -            /BS/
Am-242m                      -           2.E-12 5/     -            /BS/
Am-242                       -           3.E-08 5/     -            /BS/
Am-243                       -           2.E-12 5/     -            /BS/
Am-244m                      -           2.E-06 5/     -            /BS/
Am-244                       -           7.E-08 5/     -            /BS/
Am-245                       -           3.E-05 5/     -            /St/
Am-246m                      -           7.E-05 5/     -            /St/
Am-246                       -           4.E-05 5/     -            /St/

Cm-238                       -           4.E-07 5/     -            /St/
Cm-240                       -           2.E-10 5/     -            /BS/
Cm-241                       -           9.E-09 5/     -            /BS/
Cm-242                       -           1.E-10 5/     -            /BS/
Cm-243                       -           3.E-12 5/     -            /BS/
Cm-244                       -           4.E-12 5/     -            /BS/
Cm-245                       -           2.E-12 5/     -            /BS/
Cm-246                       -           2.E-12 5/     -            /BS/
Cm-247                       -           2.E-12 5/     -            /BS/
Cm-248                       -           6.E-13 5/     -            /BS/
Cm-249                       -           6.E-06 5/     -            /BS/

Bk-245                       -           5.E-07        -            /St/
Bk-246                       -           1.E-06        -            /St/
Bk-247                       -           2.E-12        -            /BS/
Bk-249                       -           9.E-10        -            /BS/
Bk-250                       -           2.E-07        -            /BS/

Cf-244                       -           2.E-07 5/   2.E-07 5/      /St/St
Cf-246                       -           4.E-09 5/   4.E-09 5/      /St/St
Cf-248                       -           4.E-11 5/   5.E-11 5/      /BS/St
Cf-249                       -           2.E-12 5/   6.E-12 5/      /BS/BS
Cf-250                       -           5.E-12 5/   1.E-11 5/      /BS/St

                          Inhaled Air - Lung Retention Class
                        --------------------------------------   Stochastic
                             D            W            Y         or Organ 1/
Radionuclide            (microCi/mL) (microCi/mL) (microCi/mL)   (D /W /Y )
---------------         ------------ ------------ ------------   -----------
Cf-251                       -           2.E-12 5/   5.E-12 5/      /BS/BS
Cf-252                       -           1.E-11 5/   2.E-11 5/      /BS/St
Cf-253                       -           8.E-10 5/   7.E-10 5/      /St/St
Cf-254                       -           9.E-12 5/   7.E-12 5/      /St/St

Es-250                       -           3.E-07        -            /BS/
Es-251                       -           4.E-07        -            /BS/
Es-253                       -           6.E-10        -            /St/
Es-254m                      -           4.E-09        -            /St/
Es-254                       -           4.E-11        -            /BS/

Fm-252                       -           6.E-09        -            /St/
Fm-253                       -           4.E-09        -            /St/
Fm-254                       -           4.E-08        -            /St/
Fm-255                       -           9.E-09        -            /St/
Fm-257                       -           1.E-10        -            /E /

Md-257                       -           4.E-08        -            /St/
Md-258                       -           1.E-10        -            /BS/

_____________
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, K = Kidney,
    L = Liver, Sin = Stomach wall, and T = Thyroid.  A blank indicates that
    no calculations are performed for the lung retention class shown.

2/  The ICRP identifies tritiated water and carbon as having immediate
    uptake and distribution; therefore no solubility classes are
    designated.  For purposes of this table, the DAC values are shown as
    being constant, independent of solubility class.  For tritiated water,
    the inhalation DAC values allow for an additional 50% absorption
    through the skin, as described in ICRP Publication No. 30:  Limits for
    Intakes of Radionuclides by Workers.  For elemental tritium, the DAC
    values are based solely on consideration of the dose-equivalent rate
    to the tissues of the lung from inhaled tritium gas contained within
    the lung, without absorption in the tissues.

3/  A dash indicates no values given for this data category.

4/  These values are appropriate for protection from radon combined with
    its short-lived daughters and are based on information given in ICRP
    Publication 32:  Limits for Inhalation of Radon Daughters by Workers
    and Federal Guidance Report No. 11:  Limiting Values of Radionuclide
    Intake and Air Concentrations, and Dose Conversion Factors for
    Inhalation, Submersion, and Ingestion (EPA 520/1-88-020).  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 1 WL* and 1/3 WL,*
    respectively, for appropriate limiting of daughter concentrations.
    Because of the dosimetric considerations for radon, no f1 or lung
    clearance values are listed.

    *  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.

5/  For the calculations, f1 values were obtained from ICRP Publication 48:
    The Metabolism of Plutonium and Related Elements.  It is assumed that
    the effective dose equivalents for inhalation are unchanged even though
    the f1 values have changed.  This is because the contribution to organ
    dose from inhalation is dependent mainly on transfer from lung to blood
    when f1 values are small.  Also, the gastrointestinal tract dose would
    be unchanged because the fraction of activity passing through the tract
    is (1.0 - f1).


                                    Table 2

            Alternative Absorption Factors and Lung Retention Classes
                            for Specific Compounds

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Actinium/        89    Oxides, hydroxides           1.E-t3       Y
 Ac                    Halides, nitrates            1.E-03       W
                       All others                   1.E-03       D

Aluminum/        13    Oxides, hydroxides,          1.E-02       W
 Al                      carbides, halides,
                         nitrates, elemental form
                       All others                   1.E-02       D

Americium/       95    All forms                    1.E-03       W
 Am

Antimony/        51    Oxides, hydroxides, halides, 1.E-01       D
 Sb                      sulphides, sulphates,
                         nitrates
                       All others                   1.E-02       W

Arsenic/         33    All forms                    5.E-01       W
 As

Astatine/        85    All (as a halide)            1.E+00       W or D;
 At                                                               dependent
                                                                  upon
                                                                  associated
                                                                  element

Barium/          56    All forms                    1.E-01       D
 Ba

Berkelium/       97    All forms                    5.E-04       W
 Bk

Beryllium/        4    Oxides, halides, nitrates    5.E-03       Y
 Be                    All others                   5.E-03       W

Bismuth/         83    All except nitrates          5.E-02       W
 Bi                    Nitrates                     5.E-02       D

Bromine/         35    Bromides                     1.E+00       W or D;
 Br                                                               dependent
                                                                  upon
                                                                  associated
                                                                  element

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Cadmium/         48    Oxides, hydroxides           5.E-02       Y
 Cd                    Sulphates, halides           5.E-02       W
                       All others                   5.E-02       D

Calcium/         20    All forms                    3.E-01       W
 Ca

Californium/     98    Oxides, hydroxides           1.E-03       Y
 Cf                    All others                   1.E-03       W

Carbon/           6    Oxides 1/                                 D
 C                     Organic (11C)                1.E+00       W
                       Organic (14C)                1.E+00       W

Cerium/          58    Oxides, hydroxides,          3.E-04       Y
 Ce                      fluorides
                       All others                   3.E-04       W

Cesium/          55    All forms                    1.E+00       D
 Cs

Chlorine/        17    Chloride                     1.E+00       W or D;
                                                                  dependent
                                                                  upon
                                                                  associated
                                                                  element

Chromium/        24    Oxides, hydroxides           1.E-01       Y
 Cr                    Halides, nitrates            1.E-01       W
                       All others                   1.E-01       D

                       Ingestion 2/
                       Trivalent                    1.E-02
                       Hexavalent                   1.E-01

Cobalt/          27    Oxides, hydroxides, halides, 5.E-02       Y
 Co                      nitrates
                       All others                   5.E-02       W
                       Ingestion only 2/            3.E-01

Copper/          29    Oxides, hydroxides           5.E-01       Y
 Cu                    Sulphites, halides, nitrates 5.E-01       W
                       All others                   5.E-01       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Curium/          96    All forms                    1.E-03       W
 Cm

Dysprosium/      66    All forms                    3.E-04       W
 Dy

Einsteinium/     99    All forms                    5.E-04       W
 Es

Erbium/          68    All forms                    3.E-04       W
 Er

Europium/        63    All forms                    1.E-03       W
 Eu

Fermium/        100    All forms                    5.E-04       W
 Fm

Fluorine/         9    Fluoride                     1.E+00       Y, W, or D;
 F                                                                dependent
                                                                  upon
                                                                  associated
                                                                  element

Francium/        87    All forms                    1.E+00       D
 Fr

Gadolinium/      64    Oxides, hydroxides,          3.E-04       W
 Gd                      fluorides
                       All others                   3.E-04

Gallium/         31    Oxides, hydroxides,          1.E-03       W
 Ga                      carbides, halides, nitrates
                       All others                   1.E-03       D

Germanium/       32    Oxides, sulphides, halides   1.E+00       W
 Ge                    All others                   1.E+00       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Gold/            79    Oxides, hydroxides           1.E-01       Y
 Au                    Halides, nitrates            1.E-01       W
                       All others                   1.E-01       D

Hafnium/         72    Oxides, hydroxides, halides, 2.E-03       W
 Hf                      carbides, nitrates
                       All others                   2.E-03       D

Holmiuin/        67    All forms                    3.E-04       W
 Ho

Hydrogen/         1    Water, elemental             1.E+00
 H

Indium/          49    Oxides, hydroxides, halides  2.E-02       W
 In                    All others                   2.E-02       D

Iodine/          53    All forms                    1.E+00       D

Iridium/         77    Oxides, hydroxides           1.E-02       Y
 Ir                    Halides, nitrates,           1.E-02       W
                         metallic form
                       All others                   1.E-02       D

Iron/            26    Oxides, hydroxides, halides  1.E-01       W
 Fe                    All others                   1.E-01       D

Lanthanum/       57    Oxides, hydroxides           1.E-03       W
 La                    All others                   1.E-03       D

Lead/            82    All forms                    2.E-01       D
 Pb

Lutetium/        71    Oxides, hydroxides,          3.E-04       Y
 Lu                      fluorides
                       All others                   3.E-04       W

Magnesium/       12    Oxides, hydroxides,          5.E-01       W
 Mg                      carbides, halides, nitrates
                       All others                   5.E-01       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Manganese/       25    Oxides, hydroxides, halides, 1.E-01       W
 Mn                      nitrates
                       All others                   1.E-01       D

Mendelevium/    101    All forms                    5.E-04       W
 Md

Mercury/         80    Oxides, hydroxides, halides, 2.E-02       W
 Hg                      nitrates, sulphites
                       Sulphates, elemental form    2.E-02       D
                       Organic forms                1.E+00       D
                       Vapor 1/                                  D

Molybdenum/      42    Oxides, hydroxides, MoS2     5.E-02       Y
                       All others                   8.E-01       D

                       Ingestion 2/
                       MoS2                         5.E-02
                       All Others                   8.E-01

Neodymium/       60    Oxides, hydroxides,          3.E-04       W
 Nd                      carbides, fluorides
                       All others                   3.E-04       Y

Neptunium/       93    All forms                    1.E-03       W
 Np

Nickel/          28    Oxides, hydroxides           5.E-02       W
 Ni                    All others (vapor) 1/                     D

Niobium/         41    Oxides, hydroxides           1.E-02       Y
 Nb                    All others                   1.E-02       W

Osmium/          76    Oxides, hydroxides           1.E-02       Y
 Os                    Halides, nitrates            1.E-02       W
                       All others                   1.E-02       D

Palladium/       46    Oxides, hydroxides           5.E-03       Y
 Pd                    Nitrates                     5.E-03       W
                       All others                   5.E-03       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Phosphorus/      15    Phosphates                   8.E-01       W or D;
 P                                                                dependent
                                                                  upon
                                                                  associated
                                                                  element

Platinum/        78    All forms                    1.E-02       D
 Pt

Plutonium/       94    Oxides, hydroxides           1.E-05       Y
 Pu                    Nitrates                     1.E-04       W
                       All other                    1.E-03       W
                       [Note:  Use same
                         values for
                         ingestion]

Polonium/        84    Oxides, hydroxides, nitrates 1.E-01       W
                       All others                   1.E-01       D

Potassium/       19    All forms                    1.E+00       D
 K

Praseodymium/    59    Oxides, hydroxides,          3.E-04       Y
 Pr                      carbides, fluorides
                       All others                   3.E-04       W

Promethium/      61    Oxides, hydroxides           3.E-04       Y
 Pm                      carbides, fluorides
                       All others                   3.E-04       W

Protactinium/    91    Oxides, hydroxides           1.E-03       Y
 Pa                    All others                   1.E-03       W

Radium/          88    All forms                    2.E-01       W
 Ra

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Rhenium/         75    Oxides, hydroxides,          8.E-01       W
 Re                      halides, nitrates
                       All others                   8.E-01       D

Rhodium/         45    Oxides, hydroxides           5.E-02       Y
 Rh                    Halides                      5.E-02       W
                       All others                   5.E-02       D

Rubidium/        37    All forms                    1.E+00       D
 Rb

Ruthenium/       44    Oxides, hydroxides           5.E-02       Y
 Ru                    Halides                      5.E-02       W
                       All others                   5.E-02       D

Samarium/        62    All forms                    3.E-04       W
 Sm

Scandium/        21    All forms                    1.E-04       Y
 Sc

Selenium/        34    Oxides, hydroxides, carbides 8.E-01       W
                       All others                   8.E-01       D
                       Ingestion only 2/            5.E-02

Silicon/         14    Ceramic forms                1.E-02       Y
 Si                    Oxides, hydroxides,          1.E-02       W
                         carbides, nitrates
                       All others                   1.E-02       D

Silver/          47    Oxides, hydroxides           5.E-02       Y
 Ag                    Nitrates, sulphides          5.E-02       W
                       All others, elemental form   5.E-02       D

Sodium/          11    All forms                    1.E+00       D
 Na

Strontium/       38    SrTiO3                       1.E-02       Y
 Sr                    All others (soluble)         3.E-01       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Sulfur/          16    All Inorganic                8.E-01       D
                       Elemental Form               8.E-01       W
                       Gases                        1.E+00       D

                       Ingestion 2/
                       All inorganic                1.E-01

Tantalum/        73    Oxides, hydroxides, halides, 1.E-03       Y
 Ta                      carbides, nitrates,
                         nitrides
                       All others                   1.E-03       W

Technetium/      43    Oxides, hydroxides,          8.E-01       W
 Tc                      halides, nitrates
                       All others                   8.E-01       D

Tellurium/       52    Oxides, hydroxides, nitrates 2.E-01       W
 Te                    All others                   2.E-01       D

Terbium/         65    All forms                    3.E-04       W
 Tb

Thallium/        81    All forms                    1.E+00       D
 Tl

Thorium/         90    Oxides, hydroxides           2.E-04       Y
 Th                    All others                   2.E-04       W

Thulium/         69    All forms                    3.E-04       W
 Tm

Tin/             05    Oxides, hydroxides, halides, 2.E-02       W
 Sn                      nitrates, sulphides,
                         Sn3(PO4)4
                       All others                   2.E-02       D

Titanium/        22    SrTiO3                       1.E-02       Y
 Ti                    Oxides, hydroxides,          1.E-02       W
                         carbides, halides, nitrates
                       All others                   1.E-02       D

                                                                Lung
 Element/      Atomic                                           Retention
  Symbol       Number         Compound                f1        Class
----------     ------  -----------------------      ------      ---------
Tungsten/        74    Ingestion 2/
 W                     Tungstic acid                1.E-02
                       All others                   3.E-01

Uranium/         92    UO2, U3O8                    1.E-03       Y
 U                     UO3, tetravalent compounds   5.E-02       W
                       UF6, uranyl compounds        5.E-02       D

Vanadium/        23    Oxides, hydroxides,          1.E-02       W
 V                       carbides, halides
                       All others                   1.E-02       D

Ytterbium/       70    Oxides, hydroxides,          3.E-04       Y
 Yb                      fluorides
                       All others                   3.E-04       W

Yttrium/         39    Oxides, hydroxides           1.E-04       Y
 Y                     All others                   1.E-04       W

Zinc/            30    All forms                    5.E-01       Y
 Zn

Zirconium/       40    Carbides                     2.E-03       Y
                       Oxides, hydroxides,          1.E-03       W
                         halides, nitrates
                       All others                   1.E-03       D

______________
1/   A dash indicates no data for the value shown.
2/   For ingestion, no lung retention classes are listed.


                                   Table 3

     Derived Air Concentrations (DAC) for Workers from External Exposure
            During Immersion in a Contaminated Atmospheric Cloud

                                                            Air Immersion
           Radionuclide             Half-Life               DAC (microCi/mL)
           ------------             ---------               ----------------
           C-11                     20.48 min                 4.E-06

           N-13                     9.97 min                  4.E-06
           N-16                     7.13 s                    7.E-07

           O-15                     122.24 s                  4.E-06

           F-18 1/                  109.74 min                4.E-06

           Na-24 1/                 15.00 h                   9.E-07

           Mg-27 2/                 9.458 min                 5.E-06

           Al-28 2/                 2.240 min                 2.E-06

           Cl-38 1/                 37.21 min                 3.E-06

           Ar-37                    35.02 d                   3.E-00
           Ar-39                    269 yr                    2.E-04 3/
           Ar-41                    1.827 h                   3.E-06

           K-43 1/                  22.6 h                    5.E-06

           Ca-49 2/                 8.719 min                 1.E-06

           Sc-44 1/                 3.927 h                   2.E-06
           Sc-46m 2/                18.72 s                   5.E-05

           Ti-45 1/                 3.08 h                    5.E-06
           Ti-51 2/                 5.752 min                 1.E-05

           V-52 2/                  3.75 min                  3.E-06

           Cr-49 1/                 42.09 min                 5.E-06

           Mn-52m 1/                21.4 min                  2.E-06
           Mn-56 1/                 2.5785 h                  2.E-06
           Mn-57 2/                 1.47 min                  6.E-05

           Co-60m 1/                10.47 min                 1.E-03

           Ni-57 1/, 4/             36.08 h                   2.E-06
           Ni-65 1/, 5/             2.520 h                   8.E-06

                                                            Air Immersion
           Radionuclide             Half-Life               DAC (microCi/mL)
           ------------             ---------               ----------------
           Cu-61 1/                 3.408 h                   5.E-06
           Cu-62 2/                 9.74 min                  5.E-06

           Ga-66 1/                 9.40 h                    2.E-06
           Ga-68 1/                 68.0 min                  5.E-06
           Ga-72 1/                 14.1 h                    1.E-06

           Se-73 1/                 7.15 h                    4.E-06

           Br-77 1/                 57.04 h                   1.E-05 6/
           Br-8O 1/                 17.4 min                  5.E-05
           Br-82 1/                 35.30 h                   1.E-06
           Br-84 1/                 31.80 min                 2.E-06
           Br-85 2/                 172 s                     5.E-05

           Kr-79                    35.04 h                   2.E-05
           Kr-81                    2.1E+05 yr                5.E-04
           Kr-83m                   1.83 h                    5.E-02
           Kr-85                    10.72 yr                  1.E-04 3/
           Kr-85m                   4.48 h                    3.E-05
           Kr-87                    76.3 min                  5.E-06
           Kr-88                    2.84 h                    2.E-06
           Kr-89                    3.16 min                  2.E-06
           Kr-90                    32.32 s                   3.E-06

           Rb-81 1/                 4.58 h                    8.E-06
           Rb-82 2/                 1.25 min                  2.E-06
           Rb-88 1/                 17.8 min                  7.E-06
           Rb-89 1/                 15.44 min                 2.E-06
           Rb-90 2/                 157 s                     2.E-06
           Rb-90m 2/                258 s                     1.E-06

           Sr-85m 1/                67.66 min                 2.E-05
           Sr-87m 1/                2.805 h                   6.E-05
           Sr-92 1/                 1.71 h                    3.E-06
           Sr-93 2/                 7.3 min                   2.E-06

           Y-86 1/                  14.74 h                   1.E-06
           Y-90m 1/                 3.19 h                    5.E-06 6/
           Y-91m 1/                 49.71 min                 9.E-06

           Nb-90 1/                 14.60 h                   1.E-07
           Nb-94m 2/                6.26 min                  9.E-04

                                                            Air Immersion
           Radionuclide             Half-Life               DAC (microCi/mL)
           ------------             ---------               ----------------
           Nb-97 1/                 72.1 min                  7.E-06
           Nb-97m 1/                60 s                      6.E-06

           Mo-91 2/                 15.49 min                 4.E-06
           Mo-101 1/                14.61 min                 3.E-06

           Tc-95 1/                 20.0 h                    5.E-06
           Tc-96m 1/                51.5 min                  1.E-04
           Tc-99m 1/                6.02 h                    3.E-05
           Tc-101 1/                14.2 min                  1.E-05

           Ru-105 1/                4.44 h                    5.E-06

           Rh-105m 2/               45 s                      1.E-04
           Rh-106 2/                29.92 s                   2.E-05

           Ag-108 2/                2.37 min                  2.E-04
           Ag-109m 2/               39.6 s                    1.E-03
           Ag-110 2/                24.57 s                   9.E-05

           Cd-111m 2/               48.7 min                  1.E-05
           Cd-117 1/                2.49 h                    4.E-06
           Cd-117m 1/               3.36 h                    2.E-06

           In-113m 1/               1.658 h                   2.E-05
           In-114 2/                71.9 s                    1.E-04
           In-116m 1/               54.15 min                 2.E-06
           In-117 1/                43.8 min                  7.E-06

           Sb-117 1/                2.80 h                    3.E-05
           Sb-126m 1/               19.0 min                  3.E-06
           Sb-129 1/                4.40 h                    3.E-06

           Te-133 1/                12.45 min                 5.E-06
           Te-133m 1/               55.4 min                  2.E-06
           Te-134 1/                41.8 min                  5.E-06

           I-122 2/                 3.62 min                  5.E-06
           I-128 1/                 24.99 min                 5.E-05
           I-132 1/                 2.30 h                    2.E-06
           I-134 1/                 52.6 min                  1.E-06
           I-135 1/                 6.61 h                    7.E-07 6/
           I-136 2/                 83 s                      1.E-06

                                                            Air Immersion
           Radionuclide             Half-Life               DAC (microCi/mL)
           ------------             ---------               ----------------
           Xe-122                   20.1 h                    8.E-05
           Xe-123                   2.14 h                    7.E-06
           Xe-125                   16.8 h                    2.E-05
           Xe-127                   36.406 d                  1.E-05
           Xe-129m                  8.89 d                    2.E-04
           Xe-131m                  11.84 d                   5.E-04
           Xe-133                   5.245 d                   1.E-04
           Xe-133m                  2.19 d                    1.E-04
           Xe-135                   9.11 h                    2.E-05
           Xe-135m                  15.36 min                 1.E-05
           Xe-137                   3.83 min                  2.E-05
           Xe-138                   14.13 min                 4.E-06

           Cs-126 2/                1.64 min                  4.E-06
           Cs-129 1/                32.06 h                   1.E-05 6/
           Cs-138 1/                32.2 min                  2.E-06
           Cs-139 2/                9.40 min                  1.E-05

           Ba-137m 2/               2.552 min                 7.E-06
           Ba-141 1/                18.27 min                 5.E-06
           Ba-142 1/                10.70 min                 5.E-06

           La-142 1/                95.4 min                  1.E-06

           Pr-144m 2/               7.2 min                   9.E-04

           Nd-149 1/                1.73 h                    1.E-05

           Gd-162 2/                9.7 min                   1.E-05

           Td-162 2/                7.76 min                  4.E-06

           Dy-157 1/                8.06 h                    1.E-05

           Re-182m 1/               12.7 h                    4.E-06

           Os-190m 2/               9.9 min                   3.E-06

           Ir-190m 1/               3.2 h                     8.E-05 6/

           Au-195m 2/               30.6 s                    2.E-05

                                                            Air Immersion
           Radionuclide             Half-Life               DAC (microCi/mL)
           ------------             ---------               ----------------
           Tl-200 1/                26.1 h                    3.E-06
           Tl-207 2/                4.77 min                  4.E-05 3/
           Tl-208 2/                3.053 min                 1.E-06
           Tl-209 2/                2.20 min                  2.E-06
           Tl-210 2/                1.30 min                  1.E-06

           Pb-204m 2/               66.9 min                  2.E-06

           Bi-211 2/                2.13 min                  1.E-04

           Po-211 2/                0.516 s                   5.E-04

           Rn-220                   55.61 s                   8.E-09 6/
           Rn-222                   3.824 d                   3.E-08 6/

           Th-233 2/                22.3 min                  1.E-04

           Pa-234 1/                6.70 h                    2.E-06
           Pa-234m 2/               1.17 min                  4.E-05 3/

           U-239 1/                 23.40 min                 8.E-05 6/

           Np-240 1/                65 min                    4.E-06
           Np-240m 2/               7.4 min                   1.E-05

           Am-246 1/                25.0 min                  4.E-06

______________
1/  Committed effective dose equivalent from inhalation is calculated in
    ICRP Publication 30, but the DAC value for external exposure to a
    contaminated atmospheric cloud is more restrictive than the DAC value
    for inhalation.

2/  Committed effective dose equivalent from inhalation is not calculated in
    ICRP Publication 30, but DAC value for external exposure to contaminated
    cloud should be more restrictive than DAC value for inhalation due to
    relatively short half-life of radionuclide.

3/  DAC value is determined by limit on annual dose equivalent to skin,
    rather than limit on annual effective dose equivalent.

4/  DAC value applies to radionuclide in vapor form only; DAC value for
    inhalation is more restrictive for radionuclide in inorganic form.

5/  DAC value applies to radionuclide in inorganic or vapor form.

6/  DAC value for exposure to contaminated atmospheric cloud is the same as
    DAC value for inhalation.  See footnote 4/ to Table 1 on page 24 of
    Attachment 1.


                          SURFACE RADIOACTIVITY GUIDES

____________________________________________________________________________
                                                           TOTAL 2/ 3/
  NUCLIDE 1/                REMOVABLE 2/4/           (FIXED PLUS REMOVABLE)
----------------------------------------------------------------------------
U-nat, U-235, U-238,      1,000 dpm a/100 cm 2         5,000 dpm a/100 cm 2
and associated
decay products

Transuranics,             20 dpm/100 cm 2              300 dpm/100 cm 2
Ra-226, Ra-228,
Th-230, Th-228,
Pa-231, Ac-227,
I-125, I-129

Th-nat, Th-232,           200 dpm/100 cm 2             1,000 dpm/100 cm 2
Sr-90,  Ra-223,
Ra-224, U-232,
I-126,  I-131,
I-133

Beta-gamma emitters       1,000 dpm B-T/100 cm 2      5,000 dpm B-T/100 cm 2
(nuclides with
decay modes other
than alpha emission
or spontaneous
fission) except
Sr-90 and
others noted above. 5/

----------------------------------------------------------------------------

1/  Where surface contamination by both alpha- and beta-gamma-emitting
    nuclides exists, the limits established for alpha- and
    beta-gamma-emitting nuclides should 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
    guide values.  For purposes of averaging, any square meter of surface
    shall be considered to be above the activity guide G if:  (1) from
    measurements of a representative number n of sections it is determined
    that 1/n  n Si > G, where Si is the dis/min-100 cm 2 determined from
    measurement of section i; or (2) it is determined that the sum of the
    activity of all isolated spots or particles in any 100 cm 2 area
    exceeds 3G.

4/  The amount of removable radioactive material per 100 cm 2 of surface
    area should be determined by wiping that area with dry filter or soft
    absorbent paper, applying moderate pressure, and assessing the amount
    of radioactive material on the wipe 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 should be based on the actual area and the entire surface should
    be wiped.  Except for transuranics and Ra-226, Ra-228, Ac-227, Th-228,
    Th-230, and Pa-231 alpha emitters, it is not necessary to use wiping
    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,
    including the SR-90 which is present in them.  It does not apply to
    SR-90 which has been separated from the other fission products or
    mixtures where the SR-90 has been enriched.

<<EOD>>