DOE-HDBK-1141-2001 Module 1-3, Radiological Assessor Training - Student's Guide Module 1-3
Functional areas: Radiological, Assessor Training, Regulatory Documents
This Handbook describes an implementation process for training as recommended in Implementation Guide G441.1-12, Radiation Safety Training Guide, and as outlined in DOE STD- 1098-99 DOE Radiological Control (the Radiological Control Standard - RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing training required by Title 10 Code of Federal Regulations Part 835 Occupational Radiation Protection (10 CFR 835) and training recommended by the RCS.
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Related To:
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Superseded by
A newer version replaces this document.
- DOE-HDBK-1141-2008Radiological Assessor Training (Aug 20, 2008)
Related documents
- DOE_HDBK-1141-2001Radiological Assessor Training - Foreword
- DOE-HDBK-1141-2001 Module 4-7Radiological Assessor Training - Student's Guide Module 4-7
- DOE-HDBK-1141-2001 Module 8-12Radiological Assessor Training - Student's Guide Module 8-12
- DOE-HDBK-1141-2001, Radiological Assessor Training - Overheads Part 1
- DOE-HDBK-1141-2001, Radiological Assessor Training - Overheads Part 2
- DOE-HDBK-1141-2001, Radiological Assessor Training - Overheads Part 3
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Section 1
Part 4 of 5
Radiological Assessor Training
DOE-HDBK-1141-2001
Student's Guide
Office of Environment, Safety & Health
U.S. Department of Energy
Radiological Assessor Training
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Table of Contents
Regulatory Documents..................................................................................... Module1-1
10 CFR Part 835, Background and Focus....................................................... Module 2-1
Overview of the DOE Radiological Control Manual......................................... Module 3-1
Elements of a Radiological Control Program................................................... Module 4-1
Technical Safety Requirements ...................................................................... Module 5-1
Radiological Aspects of Uranium .................................................................... Module 6-1
Radiological Aspects of Tritium ....................................................................... Module 7-1
Radiological Aspects of Plutonium .................................................................. Module 8-1
Radiological Work Permits .............................................................................. Module 9-1
Contamination Containment and Temporary Control Measures ................... Module 10-1
Radiological Work Site Mockup Demonstration ............................................ Module 11-1
Radiation-Generating Devices ...................................................................... Module 12-1
Radiological Aspects of Accelerators ............................................................ Module 13-1
Assessment Techniques ............................................................................... Module 14-1
Planning and Conducting Assessments........................................................ Module 15-1
Case Studies................................................................................................. Module 16-1
Review and Critique of Findings and Improved Writing of Findings .............. Module 17-1
Compliance-Based Versus Performance-Based Evaluations........................ Module 18-1
Field Exercise Guidelines.............................................................................. Module 19-1
Course Summary .......................................................................................... Module 20-1
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Module 1- 1
I. Introduction
II. DOE radiological health and safety
A. Policy (some key points in summary)
• Establish and maintain a system of
regulatory policy and guidance.
• Ensure appropriate training is developed and
delivered and the technical competence of
the DOE workforce.
• Establish and maintain, from the lowest to
the highest levels, line management
involvement and accountability for
Departmental radiological performance.
• Ensure radiological measurements,
analyses, worker monitoring results, and
estimates of public exposures are accurate
and appropriately made.
• Conduct radiological operations in a manner
that controls the spread of radioactive
materials and reduces exposure to the work
force and the general public and utilizes a
process that seeks exposure level as low as
reasonably achievable (ALARA).
Section 2
• Incorporate dose reduction, contamination
reduction, and waste minimization features
into the design of new facilities and
significant modifications to existing facilities
in the earliest planning stages.
• Conduct oversight to ensure Departmental
requirements are being complied with and
appropriate radiological work practices are
being implemented.
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B. History
DOE has provided numerous written standards
for on-site radiological protection, the most
recent regulation being 10 CFR Part 835,
Occupational Radiation Protection. This
regulation was preceded by:
• DOE Notice 5480.6 of June 17, 1992,
Radiological Control, which specified that the
DOE Radiological Control Manual (DOE/EH-
0256T) would supersede DOE Order
5480.11.
• DOE Order 5480.11, Radiation Protection for
Occupational Workers (effective December,
1988). The purpose was to establish
radiation protection standards and program
requirements for DOE and DOE contractors
for the protection of workers from ionizing
radiation.
The establishment of DOE radiological
protection standards did not start with these
documents. A chronology of dose limits of DOE
and its predecessor agencies, the Atomic
Energy Commission (1946-1975) and the
Energy Research and Development
Administration (1975-1977), demonstrate a
lowering of whole body dose limits over the last
50 years.
In the establishment of these dose limits, DOE
has followed recommendations of national and
international radiological protection groups,
notably the International Commission on
Radiological Protection (ICRP) and the National
Council on Radiation Protection and
Measurements (NCRP).
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C. Hierarchy of requirements
Currently within DOE there are two parallel
hierarchies of requirements:
• Rules and/or regulations (these terms are
used interchangeably in this training)
• DOE Orders
III. Rules and regulations
In response to the enforcement authority in the
Price-Anderson Amendments Act (PAAA) of 1988,
DOE is converting its contractual requirement in
orders to enforceable rules to enhance contractor
accountability for safety.
A. DOE enforcement of rules under PAAA
10 CFR Part 820 (effective on September 16,
1993) sets forth the procedures to implement the
provisions of the PAAA. Part 820 requires
contractors to comply with DOE Nuclear Safety
Requirements.
PAAA demands a “large stick” to enhance
contractor accountability for safety. Rules
provide authority for the assessment of civil and
criminal penalties and thus provide the large
stick.
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B. Penalties under Part 820
1. Civil penalties
DOE may assess civil penalties against any
person subject to Part 820, for violations of:
• Codified rules in the CFR
• Compliance orders
• Any program or plan required by a rule or
compliance order
Note: Certain nonprofit educational
institutions and other listed institutions are
exempt from assessment of civil penalties.
2. Criminal penalties
If a person subject to the Atomic Energy Act
of 1954, as amended, or Nuclear Safety
Requirements, has by action or omission
knowingly and willfully violated, caused to be
violated, attempted to violate, or conspired to
violate any section of the Atomic Energy Act
of 1954, as amended, or applicable DOE
Nuclear Safety Requirements, the person
shall be subject to criminal sanctions.
Section 3
3. The “carrot and stick” approach
DOE may provide monetary incentives in its
management and operating (M&O) contracts
for actions consistent with or exceeding
requirements, and to penalize actions and
activities that were not in compliance with
requirements.
Noncompliance with the Radiation Protection
Program can subject a contractor to PAAA
enforcement. There are provisions to
mitigate penalties for self identifying and
reporting violations.
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C. DOE Nuclear Safety Requirements
DOE Nuclear Safety Requirements are the set of
enforceable rules, regulations, or orders relating
to nuclear safety that have been adopted by
DOE (or by another agency if DOE specifically
identifies it).
Compliance orders are issued by the Secretary.
They identify a situation that violates, potentially
violates, or otherwise is inconsistent with the:
• Atomic Energy Act of 1954, as amended
• Nuclear statutes
• Nuclear Safety Requirements
Compliance orders:
• Mandate a remedy or other action
• States the reason for the remedy or other
action
D. 10 CFR Part 835
On December 14, 1993, DOE published a final
rule in the Federal Register (58 FR 65458) Title
10 Code of Federal Regulations Part 835,
Occupational Radiation Protection (10 CFR
835). On November 4, 1998 an amendment to
10 CFR 835 was published in the Federal
Register (63 FR 59663).
The purpose of 10 CFR 835 is the codification of
radiological protection requirements. It contains
“shall” statements, which are legally binding. It
also contains:
• Prescriptive language
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• Added emphasis on ALARA
• Requirements for a Radiation Protection
Program (RPP)
• Federal law
• Criminal and civil penalties for violations
E. Radiation Protection Program (10 CFR Part 835)
Each site, under Part 835, must submit a written
Radiation Protection Program (RPP).
The RPP requires careful consideration because
noncompliance may subject a contractor to
PAAA enforcement
F. Guidance documents for 10 CFR Part 835
Two types of regulatory guidance documents
have been developed:
• Guidance for implementing the provisions of
10 CFR Part 835.
• Guidance providing technical positions.
The above are available through the DOE EH-52
website at:
http://tis.eh.doe.gov/whs/rhmwp/regs.html
Unlike the requirements specifically set forth in
10 CFR Part 835, the provisions in guidance
documents are not mandatory. They are
intended solely to describe the rationale for, and
the objectives of, regulatory requirements and/or
to identify acceptable methods for implementing
regulatory requirements.
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Failure to follow a guidance document does not
in itself indicate noncompliance with a specific
requirement of the rule. A finding of
noncompliance is found for a failure to satisfy
the regulatory requirement.
Following a guidance document in the
prescribed manner will ordinarily create a
presumption of compliance with a related
regulatory requirement.
1. Technical guidance
Technical guidance describes and
disseminates technical methods and
techniques for fulfilling implementation and,
in turn, the requirements in
10 CFR Part 835. Examples of these
guidance are DOE Technical Standards and
DOE Radiological Control Technical
Positions (RCTPs).
Section 4
2. Implementation guides (IGs)
Implementation guidance is intended to
identify and make available to DOE
contractors basic program elements and
acceptable methods for implementing
specific provisions of the final rule. Thirteen
implementation guides have been developed
for 10 CFR Part 835.
G. Relationship between 10 CFR Part 835 and
10 CFR Part 20
10 CFR Part 20 is the occupational radiological
regulation issued by the Nuclear Regulatory
Commission (NRC).
The question of consistency among federal
agencies in their occupational radiological
protection regulations became a major point of
discussion during the rule making process.
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While agreeing with the goal of consistency,
DOE believes that it must promulgate its own
regulations because of the unique nature and
diversity of radiological activities within the DOE
complex. The final rule allows DOE to establish
more rigorous requirements in areas of particular
concern. Overall 10 CFR Part 835 has many
similarities as 10 CFR Part 20.
IV. DOE STD Radiological Control and Orders
A. Radiological Control
In January 1992, a memorandum was sent to the
heads of DOE elements involved in managing
radiological programs. In the memorandum, the
Secretary directed a series of initiatives to
enhance the conduct of radiological operations
within the Department of Energy. Also in this
memo, the Assistant Secretary of Environment,
Safety and Health was directed to develop a
comprehensive and definitive radiological control
manual. The DOE Radiological Control Manual
was developed to meet that directive and was
approved by the Secretary and promulgated with
DOE Notice 5480.6, Radiological Control, in July
1992.
After the issuance of 10 CFR 835 as a final rule
in December 1993, DOE Notice N441.1,
Radiological Protection for DOE Activities, was
issued on 9-30-95. This cancelled the notice
which made the Radiological Control Manual a
requirements document. However, the notice
stated that "cancelled orders that are
incorporated by reference in a contract shall
remain in effect until the contract is modified to
delete the reference.
N441.1 also retained some of the radiation
protection requirements from the Radiological
Control Manual that were not included in 10 CFR
835.
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In July, 1999, the Radiological Control Manual
was replaced by the standard, DOE-STD-1098-
99, Radiological Control. Many DOE sites
contractually must still adhere to the provisions
of either the Radiological Control Manual or the
Radiological Control Standard. Subsequent to
the 1998 amendment to 10 CFR 835, the
effective date of N441.1 has passed.
The DOE Radiological Control Standard is not
regulatory in nature. It is a guidance document
that describes DOE’s policy and expectations for
an excellent radiological control program.
1. Implementation
If a site fully implements a provision of the
DOE Radiological Control Standard, the user
will have most likely complied with any
related statutory, regulatory, or contractual
requirements. Users are cautioned that they
must review the source document (10 CFR
835) to ensure compliance.
2. Enforceability
When incorporated into contracts, the
provisions of the DOE Radiological Control
Standard or Manual are binding
requirements.
If portions of the Site-Specific Radiological
Section 5
Control Manual are incorporated in the RPP
under Part 835 and approved by DOE, they
are also binding.
B. The Site-Specific Radiological Control Manual
• The DOE Radiological Control Standard
states that a Site-Specific Radiological
Control Manual should be written and
followed.
.
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C. Relationship between 10 CFR Part 835 and the
DOE Radiological Control Standard
1. Compliance
• The Office of Enforcement and
Investigation (EH-10) will enforce 10 CFR
Part 835. It can assess fines and
penalties.
• The Program Offices will audit for both
compliance with 10 CFR 835 and
contractual agreements including the DOE
Radiological Control Standard or Manual,
Orders, etc. Results of these audits can
affect the contractor’s award fee.
2. What if there are conflicts?
10 CFR Part 835 takes precedence over
requirements of the DOE Radiological
Control Standard and orders. It is unlikely
that there will be a conflicting requirement
between the two documents, although one
document may have a requirement that is not
addressed in the other.
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It is planned that all requirements for nuclear
safety will be incorporated into rules.
3. “Shall” and “should” statements
• 10 CFR Part 835 contains “shall”
statements. “Shall” statements in Part
835 are legally binding.
Processes for exemption relief from Part
835 are set forth in Subpart E to Part 820.
If relief is requested from provisions of
Part 835, the exemption must be
considered and granted, if appropriate, by
the Assistant Secretary for Environment,
Safety and Health (EH-1).
• The use of “should” in the DOE
Radiological Control Standard recognizes
that there may be site- or facility-specific
attributes that warrant special treatment.
It also recognizes that literal compliance
with the elements and requirements of the
provision may not achieve the desired
level of radiological control performance.
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D. DOE Standards
DOE has developed several technical standards
for occupational radiation protection. Depending
on the site specific application, some standards
are required to be followed. For example, sites
which need to monitor individual external
exposures to ionizing radiation need to follow the
DOE Laboratory Accreditation Program
(DOELAP) standards. Other standards may be
incorporated by reference in the site RPP.
Other standards provide technical guidance on
specific applications, but adherence to the
standard may not be required.
Prior to conducting an assessment, the site
requirements documents must be reviewed to
determine applicable requirements.
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V. Defense Nuclear Facilities Safety Board
A. Establishment
The Atomic Energy Act of 1954 was amended by
adding Chapter 21, Defense Nuclear Facilities
Safety Board (DNFSB). This amendment
established an independent board in the
executive branch to provide oversight of some
DOE operations at DOE facilities and sites.
B. Members
The DNFSB consists of five members appointed
by the President with consent of the Senate.
The Board shall:
• Review and evaluate standards
• Investigate any event or practice at a DOE
Section 6
defense nuclear facility that the Board
determines has adversely affected or may
adversely affect public health and safety.
The Board may:
• Establish reporting requirements for the
Secretary of Energy
By evaluating how well DOE meets its
objectives, the DNFSB helps DOE achieve and
maintain excellence in radiological protection.
C. Secretary of Energy
The Secretary of Energy shall fully cooperate
with the Board.
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D. DNFSB Recommendations
DNFSB provides DOE with recommendations for
improving safety at DOE defense nuclear
facilities. Examples include:
DNFSB Recommendation 91-6 dealt with
radiological protection concerns throughout
the DOE defense nuclear facilities complex,
and identified several actions to be taken by
the Department to improve radiological
protection performance.
DNFSB Recommendation 92-7 dealt with
training and qualification at DOE sites and
facilities.
DNFSB Recommendation 98-1 dealt with
resolution of internal audit findings.
DNFSB Recommendation 99-1 dealt with
safe storage of fissionable materials.
Implementation of DOE and site commitments
made in response to DNFSB recommendations
are areas to review during an assessment.
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Module 2 - 1
I. Introduction
This module provides an overview of many of the
provisions of 10 CFR 835. For completeness,
individuals should always reference back to 10 CFR
835 for the complete text.
II. Outline of 10 CFR Part 835
Part 835 is the codification of radiological protection
requirements. Part 835 contains 14 subparts and
five appendices. The outline consists of the
following subparts:
A — General Provisions
B — Management and Administrative
Requirements
C — Standards for Internal and External Exposure
D — Reserved
E — Monitoring of Individuals and Areas
F — Entry Control Program
G — Posting and Labeling
H — Records
I — Reports to Individuals
J — Radiation Safety Training
K — Design and Control
L — Radioactive Contamination Control
M — Sealed Radioactive Source Control
N — Emergency Exposure Situations
Under 10 CFR Part 835, each site must submit a
Radiation Protection Program (RPP).
Part 835 helps to ensure that DOE facilities are
operated in a manner such that occupational
radiological exposure to workers is maintained
within acceptable limits and as low as is reasonably
achievable (ALARA).
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A. Subpart A - General Provisions
Subpart A contains the scope of the rule. The
rule in this part establishes radiological
protection standards, limits, and program
requirements for protecting individuals from
ionizing radiation resulting from the conduct of
DOE activities.
It also includes activities excluded from the
provisions of the rule. Activities that are
excluded include the following (summarized):
• Activities regulated through a license by the
Nuclear Regulatory Commission (NRC) or a
state under an agreement with the NRC.
• Activities conducted under the authority of the
Director, Naval Nuclear Propulsion Program.
• Specified activities conducted under the
Nuclear Explosives and Weapons Surety
Program.
• Radioactive material transportation.
• DOE activities in other countries with
acceptable radiation protection program.
• Background radiation.
Section 7
Occupational doses received as a result of
excluded activities and radioactive material
transportation, as listed above, shall be
considered when determining compliance with
the occupational dose limits (835.202 and
835.207), and with the limits for the embryo/fetus
(835.206).
Subpart A also addresses:
• Definitions
• Radiological units (Curie, rad, roentgen, rem,
and multiples)
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B. Subpart B - Management and Administrative
Requirements
The RPP shall:
• Include formal plans and measures for
applying the ALARA process to occupational
exposures.
• Specify the existing and/or anticipated
operational task.
• Address, but not be limited to, each
requirement in Part 835.
• Include plans, schedules, and other
measures for achieving compliance.
DOE may direct or make modifications to an
RPP. An initial RPP or update shall be
considered approved 180 days after its
submission unless rejected by DOE at an earlier
date.
Compliance with 835.402(d) for radiobioassay
program accreditation shall be achieved no later
than January 1, 2002.
Internal Audits (10 CFR 835.102)
Internal audits of the radiation protection
program, including examination of program
content and implementation, shall be conducted
through a process that ensures that all functional
elements are reviewed no less frequently than
every 36 months. This training material and
DOE G 441.1, Management and Administration
of Radiation Protection Programs Guide, provide
guidance on DOE's expectations.
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Education, Training and Skills (10 CFR 835.103)
Individuals responsible for developing and
implementing measures necessary for ensuring
compliance with the requirements of this part
shall have the appropriate education, training,
and skills to discharge these responsibilities.
DOE STD-1107-97 Knowledge, Skills, and
Abilities for Key Radiation Protection Positions at
DOE Facilities, provides guidance on DOE's
expectations.
Written Procedures (10 CFR 835.104)
Written procedures are required, as necessary,
to ensure compliance with 835, commensurate
with radiological hazards and education, training
and skills of exposed individuals.
C. Subpart C - Standards for Internal and External
Exposure
This subpart addresses limits for:
• General employees (occupational)
• Embryos/fetus of declared pregnant worker
(i.e., A woman who has voluntarily declared
to her employer, in writing, her pregnancy for
the purpose of being subject to the
occupational dose limits to the embryo/fetus.
This declaration may be revoked, in writing,
at any time by the declared pregnant worker.)
• Occupationally exposed minors
• General public in a controlled area
It also addresses:
• Planned special exposures
• Nonuniform exposures of the skin
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• Concentrations of radioactive material in air
1. Summary of dose limits
10 CFR Part 835 employs the rem unit for
several different physical quantities. For
information about these quantities refer
participants to page 1 of handouts, “Dosimetric
Quantities in 10 CFR Part 835.”
Exposed Individual Annual Limit
General Employee: Whole Body (internal and external) (TEDE) 5.0 rem
General Employee: Lens of Eye (DE) 15.0 rem
Section 8
General Employee: Extremity (below elbow and knees) and skin (SDE) 50.0 rem
General Employee: Any Organ or Tissue (other than lens of eye) (DDE + CDE) 50.0 rem
Declared Pregnant Worker: Embryo/Fetus (gestation period) (DE) 0.5 rem
Occupationally Exposed Minors (under age 18): (TEDE) 0.1 rem *
Members of the Public in Controlled Areas: (TEDE) 0.1 rem
• And 10% of other general employee limits.
2. Planned special exposures (PSEs)
It is acknowledged that unusual conditions
can arise in which higher-than-normal doses
can be justified. In these well-planned, well-
controlled, and highly infrequent and unusual
conditions operating management would be
permitted to allow specified individual doses
exceeding the occupational limit, such as 5
rem per year.
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The term "unusual conditions" is made clear
by specifying that alternatives which would
preclude exposures higher than the
prescribed dose limits must be either
unavailable or impractical.
10 CFR 835.204 specifies requirements for
annual and lifetime dose from PSEs. It also
specifies requirements for determining
previous individual exposures prior to
allowing a PSE.
Every PSE must be approved in advance by
DOE and requires the informed consent of
the employee involved.
3. Concentration of radioactive material in air
Appendices A and C contain the derived air
concentration (DAC) values used in the
control of occupational exposure to airborne
radioactive material.
DACs are listed in appendices A and C of 10
CFR 835. For intakes (appendix A), they are
the airborne concentration that equals the
annual limit on intake (ALI) divided by the
volume of air breathed by an average worker
for a working year of 2000 hours (assuming a
breathing volume of 2400 m3).
The ALI is the smaller value of intake of a
given radionuclide in a year by a
standardized man that would result in a
CEDE of 5 rems or a CDE of 50 rems to any
individual organ or tissue.
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Appendix C contains DACs for controlling
external dose from being immersed in a cloud
of airborne radioactive material.
Estimation of internal dose shall be based on
bioassay data rather than air concentration
values unless bioassay data are:
• Unavailable (e.g., radon or very short lived
radioisotopes)
• Less accurate than internal dose
estimates based on representative air
concentration values
• Inadequate
E. Subpart D - Reserved
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E. Subpart E - Monitoring of Individuals and Areas
This subpart addresses:
• General requirements
• Instrumentation
• Individual monitoring - external
• Individual monitoring - internal
• Air monitoring
• Receipt of packages containing radioactive
material
1. General requirements (10 CFR 835.401)
Monitoring of individuals and areas shall
be performed to:
• Demonstrate compliance with Part
835.
• Document radiological conditions.
• Detect changes in the radiological
conditions.
• Detect the gradual buildup of
radioactive material.
• Verify the effectiveness of engineering
and process controls in containing
radioactive material and reducing
radiation exposure.
• Identify and control potential sources
of individual exposure to radiation
and/or radioactive material.
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2. Instrumentation
Instruments and equipment used for
monitoring and contamination control shall
be:
• Periodically maintained and calibrated
on an established frequency.
• Appropriate for the type(s), levels, and
energies of the radiation(s)
encountered.
• Appropriate for existing environmental
conditions.
• Routinely tested for operability.
3. Individual monitoring - external (10 CFR
835.402)
For the purpose of monitoring individual
exposure to external radiation, personnel
dosimetry shall be provided to and used
by:
• Radiological Workers likely to receive:
– An effective dose equivalent to the
whole body of 0.1 rem (100 mrem)
or more in a year
– A shallow dose equivalent to the
skin or to any extremity of 5 rem or
more in a year
– A lens of the eye dose equivalent
of 1.5 rem or more in a year
• Declared Pregnant Workers who are
likely to receive from external sources
a dose equivalent to the embryo/fetus
in excess of 10 percent of the
applicable limit.
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• Members of the public in a controlled
area and occupationally exposed
minors likely to receive, in one year,
from external sources, a dose in
excess of 50 percent of the applicable
limits.
• Individuals entering a High or Very
High Radiation Area.
DOE Laboratory Accreditation for
Personnel Dosimetry is required for
external dose monitoring programs
implemented to demonstrate compliance
with 10 CFR 835.
4. Individual monitoring - internal (10 CFR
835.402)
Internal dose evaluation programs
(including routine bioassay programs)
shall be conducted for:
• Radiological Workers who, under
typical conditions, are likely to receive
0.1 rem or more committed effective
dose equivalent from all occupational
radionuclide intakes in a year.
• Declared Pregnant Workers likely to
receive an intake or intakes resulting in
a dose equivalent to the embryo/fetus
in excess of 10 percent of the limit.
• Members of the public in a controlled
area and occupationally exposed
minors who are likely to receive a
committed effective dose equivalent in
excess of 50 percent of the limit from
all intakes in a year.
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DOE Laboratory Accreditation for
Radiobioassay is required for internal dose
monitoring programs implemented to
demonstrate compliance with 10 CFR 835.
5. Air monitoring (10 CFR 835.403)
Measurements of radioactivity concentrations
in the ambient air of the workplace shall be
performed as follows:
• Air sampling shall be performed in
occupied areas where an individual is
likely to receive an exposure of 40 DAC-
hrs or more in a year (i.e. an annual
intake of 2 percent or more of the specific
ALI value) for the mixture of isotopes.
• Samples shall be taken as necessary to
characterize the levels or concentration of
airborne radioactive material when
respirators are worn for radiation
protection purposes.
• Real-time air monitoring shall be
performed when there is a need to alert
potentially exposed individuals to
unexpected increases in airborne
radioactivity levels such that immediate
action is necessary in order to minimize or
stop inhalation exposures.
6. Receipt of Packages Containing Radioactive
Material (10 CFR 835.405)
Establishes requirements to monitor certain
Section 10
types of packages and sets a time limit of not
later than 8 hours after the beginning of the
working day following receipt of the package.
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F. Subpart F - Entry Control Program (10 CFR
835.501)
Subpart F addresses entry into:
• Radiological Areas
• High Radiation Areas
• Very High Radiation Areas
1. Radiological Areas
The degree of control shall be commensurate
with existing and potential radiological
hazards within the area.
One or more of the following methods
shall be used to ensure control:
• Signs and barricades
• Control devices on entrances
• Conspicuous visual and/or audible
alarms
• Locked entrance ways
• Administrative controls
“No control(s) shall be installed at any
radiological area exit that would prevent
rapid evacuation of personnel under
emergency conditions.”
2. High Radiation Areas
A High Radiation Area is an area where
radiation levels exist such that an
individual could exceed a deep dose
equivalent to the whole body of 0.1 rem in
any one hour at 30 centimeters from the
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source or from any surface that the
radiation penetrates.
If an individual receive a deep dose
equivalent exceeding 1.0 rem in an hour
(at 30 cm), a High Radiation Area shall
have one or more of the following:
• A control device that prevents entry to
the area when high radiation levels
exist or that, upon entry, causes the
radiation level to be reduced below
that level that defines a High Radiation
Area.
• A device that functions automatically to
prevent use or operation of the
radiation source or field while
individuals are in the area.
• A control device that energizes a
conspicuous visible or audible alarm
signal so that the individual entering
the High Radiation Area and the
supervisor of the activity are made
aware of the entry.
• Entryways that are locked. During
periods when access to the area is
required, positive control over each
entry is maintained.
• Continuous direct or electronic
surveillance that is capable of
preventing unauthorized entry.
• A control device generating audible
and visual 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 are or activation of a secondary
control device that will prevent use or
operation of the source.
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3. Very High Radiation Areas
A Very High Radiation Area is an area in
which an individual could receive a dose
in excess of 500 rad in one hour at 1
meter from the radiation source or from
any surface that the radiation penetrates.
In addition to the requirements for a High
Radiation Area, additional measures shall
be implemented to ensure individuals are
not able to gain unauthorized access to
Very High Radiation Areas.
“No control(s) shall be established in a
High or Very High Radiation Area that
would prevent rapid evacuation of
personnel.”
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G. Subpart G - Posting and Labeling
Subpart G addresses the general requirements
for signs:
• Yellow background
• Black or magenta radiation symbol
• Clear and conspicuous signs
In addition, Subpart G addresses specific posting
requirements for:
Section 11
• Controlled Areas
• Radiation Areas
• High Radiation Areas
• Very High Radiation Areas
• Airborne Radioactivity Areas
• Contamination Areas
• High Contamination Areas
• Radioactive Material Areas
This subpart also addresses exceptions to
posting and labeling.
H. Subpart H - Records
Subpart H addresses requirements for records
documenting compliance with Part 835 and with
the Radiation Protection Program.
Records that are specifically required include
those necessary to demonstrate compliance with
the ALARA provisions of the rule.
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10 CFR 835 also requires that certain records be
maintained, including records of:
• Individual monitoring
• Sealed source inventory and control
• Results of surveys for the release of material
and equipment
• Results of specified monitoring for radiation
and radioactive material
• Maintenance and calibration of radiation
monitoring instruments
• Internal audits
Each individual’s training as a general employee
and as a Radiological Worker must be recorded.
Where appropriate, demonstration and
documentation of proficiency is required.
Refer to 10 CFR 835 Subpart H for a complete
listing of required records.
DOE G 441.1-11, Occupational Radiation
Protection Record-Keeping and Reporting Guide,
provides additional guidance on record-keeping
requirements, including reference to DOE O
231.1, Change 2, Environment, Safety and
Health Reporting, and DOE M 231.1-1, Change
2, Environment, Safety and Health Reporting
Manual. This order and manual specify radiation
protection reporting requirements that may be
applicable to the site or facility being assessed.
I. Subpart I - Reports to Individuals (10 CFR
835.801)
Subpart I addresses reports to individuals and
their accessibility to reports, including:
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On an annual basis, each DOE or DOE
contractor-operated site or facility must provide
each individual monitored for occupational
exposure a radiation dose report of his/her
occupational exposure at that site or facility.
Upon the request from an individual terminating
employment, records of exposure shall be
provided to that individual as soon as the data
are available, but not later than 90 days after
termination. A written estimate of the radiation
dose received by that employee based on
available information shall be provided at the
time of termination, if requested.
J. Subpart J - Radiation Safety Training
This subpart addresses radiation safety training.
The tailored approach to training requirements
are based on:
• Unescorted access to or receiving
occupational dose in controlled areas (e.g.,
General Employees)
• Unescorted access to radiological areas or
unescorted assignment as Radiological
Workers
Requirements of Part 835 include:
• Verification by examination for certain training
(e.g., Radiological Worker Training)
• Intervals of training not to exceed twenty four
months
• List of topics which must be included in
training
• Provisions for limited use of escorts in lieu of
training
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DOE G 441.1-12, Radiation Safety Training
Guide, provides additional guidance on DOE's
expectations on radiation safety training.
K. Subpart K - Design and Control
Section 12
Subpart K addresses added emphasis on facility
and equipment design and administrative
controls to maintain radiological exposures
ALARA.
1. Facility design and modifications (10 CFR
835.1001)
During the design of new facilities or
modification of old facilities, the following
objectives shall be adopted:
• Optimal methods shall be used to assure
ALARA
• Maintain exposure levels below an
average of 0.5 mrem/hr
• Avoid release of radioactivity to the
workplace atmosphere
• The design or modification of a facility and
the selection of materials shall include
features that facilitate operations,
maintenance, decontamination, and
decommissioning
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2. Workplace controls (10 CFR 835.1003)
During routine operations, the combination of
physical design features and administrative
control shall provide that:
• The anticipated occupational dose to
general employees shall not exceed the
limits
• The ALARA process is utilized for
personnel exposures to ionizing radiation
L. Subpart L - Radioactive Contamination Control
1. Control of material and equipment
This section addresses the requirements for
release of materials and equipment from
radiological areas to controlled areas.
Releases to uncontrolled areas are addressed
in DOE O 5400.5. Some of the provisions:
• Specifies conditions for material and
equipment in contamination areas (CAs),
high contamination areas (HCAs), and
airborne radioactivity areas (ARAs) to be
released to a controlled area
• Addresses movement of material and
equipment with removable surface
contamination, on-site from one
radiological area for immediate placement
in another radiological area
• Specifies conditions for material and
equipment with fixed contamination to be
released for use in controlled areas
outside of radiological areas
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Control of Areas (10 CFR 835.1102) addresses
• Prevention of inadvertent transfer or
removal of contamination to locations
outside radiological areas under
normal conditions
• Where contamination levels exceed
values in Appendix D, the area is
controlled commensurate with hazards
• Areas with fixed contamination
exceeding radioactivity values may be
located outside radiological areas,
provided certain controls, conditions,
or provisions are met
• Personnel monitoring for
contamination upon exiting CAs,
HCAs, or ARAs
• Use of protective clothing in CAs and
HCAs
M. Subpart M - Sealed Radioactive Source Control
Sealed radioactive sources shall be used,
handled and stored in a manner commensurate
with the hazard.
Specifies values (Appendix E) for sources which
must be inventoried and leak tested at intervals
not to exceed six months.
N. Subpart N - Emergency Exposure Situations
This subpart addresses:
• Employees who have exceeded dose limits
as result of authorized emergency exposure
• Nuclear accident dosimetry
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Individuals whose occupational
exposures have exceeded any limits as a
result of an authorized emergency
exposure may be permitted to return to
work provided that certain conditions are
met.
Nuclear accident dosimetry
Nuclear accident dosimetry involves
installations possessing sufficient
quantities of fissile material to constitute a
critical mass, and shall include;
Section 13
• Method to conduct initial screening of
personnel involved
• Method and equipment for analysis of
biological materials
• A system of fixed nuclear accident
dosimeter units
• Personal nuclear accident dosimeters
T
T
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Module 3–1
I. Introduction
II. DOE Radiological Control Standard
The DOE Radiological Control Standard is written
for line management. It is designed to assist line
managers in fulfilling their duties and responsibilities
for implementing an occupational radiation
protection program.
It is also designed to assist site/facility workers in
having the information they need to be responsible
for their own radiological exposures and to help
ensure that the controls are in place to eliminate
any releases, unplanned exposures or uptake, and
to apply ALARA principles. The emphasis is on
teamwork and support from line management.
The Radiological Control Standard may be
considered as an occupational radiation protection
good practices document. Individual sites may
have contractual commitments to implement
sections of the standard.
III. Chapter 1, Excellence in Radiological Control
This chapter defines the roles of DOE and the
contractors in achieving the goal of radiological
control excellence. It consists of the following five
sections:
• DOE Radiological Control Standard
• Leadership in Radiological Control
• Improving Radiological Control Performance
• Contractor Radiological Control Organization
• DOE Management
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A. DOE Radiological Control Standard
The contractor is responsible for implementing
an occupational radiation protection program.
To assist this effort, they may develop a Site
Radiological Control Standard Implementation
Plan. The Site-Specific Radiological Control
Standard, which is developed from the
Implementation Plan, does not require DOE
approval.
B. Leadership in Radiological Control
Commitment of senior management to
radiological control is defined in this section of
the Standard.
The responsibilities and accountability of each
individual for ALARA and radiological excellence
is emphasized.
Worker responsibilities and the concepts of
conduct of radiological operations are clearly
defined.
C. Improving Radiological Control Performance
The use of critiques as a management tool,
rather than as a method to “fix blame” or “shoot
the messenger,” and the importance of real root
cause identification are emphasized. Over 20
radiological performance indicators are identified
that are tools designed to assist managers in
focusing their priorities and attention on
radiological control performance.
D. Contractor Radiological Control Organization
This section discusses the contractor’s
radiological control organization and the
qualifications of the Radiological Control
Manager.
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E. DOE Management
This section discusses the roles and
responsibilities of DOE management for
providing guidance and performance evaluation
of radiological control programs.
IV. Chapter 2, Radiological Standards
This chapter deals with administrative control dose
Section 14
limits, contamination control and control levels, and
posting.
A. Administrative Control Levels (ACLs) and Dose
Limits
Lifetime control levels and dose limits for
Radiological Workers, members of the public,
embryos/fetuses, and special control levels are
discussed in this section.
For most facilities an ACL of 500 millirem or less
will be challenging for Radiological Workers.
Individual occupational doses, in rem, should be
kept below the individual's age in years.
B. Contamination Control and Control Levels
In this section, personnel contamination control,
removable and fixed contamination control
levels, and airborne radioactivity control levels
are given.
C. Posting
Posting requirements are presented in this
section and include several non-regulatory areas
including: Radiological Buffer Areas,
Underground Radioactive Material Areas, and
Soil Contamination Areas.
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V. Chapter 3, Conduct of Radiological Work
The planning of radiological work, work preparation
(e.g., Radiological Work Permits), and the
requirements for the entry to and exit from the
various types of controlled areas are contained in
this chapter. Also covered are: radiological work
performance, the aspects of radiological work in
different operations with radiation-generating
equipment, and construction and restoration
projects.
A. Planning Radiological Work
This section emphasizes that the conduct of
radiological work is a line responsibility. Worker
responsibility, along with systematic planning,
provides the necessary information for safe
radiological work. Of fundamental importance is
the requirement to plan work with an emphasis
on ALARA principles.
B. Work Preparation
In this section, the Radiological Work Permit
(RWP) is discussed. This chapter states that the
RWP is the key to any particular radiological
operation, and preplanning is essential.
C. Entry and Exit Requirements
The minimum requirements for entry into and
exit from defined radiological areas and other
non-regulatory areas are discussed in this
section.
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D. Radiological Work Controls
This section discusses radiological work as a
team effort involving the Radiological Workers,
their supervisors, and Radiological Control
personnel. The DOE Radiological Control
Standard discusses stop-radiological work
authority for Radiological Control Technicians
(RCTs), their supervisors, line supervision, and
workers through their supervisors because of:
• Inadequate radiological controls
• Radiological controls not being implemented
• A radiological control hold point not being
satisfied
DOE O 440.1A, Worker Protection Program for
DOE Federal and Contractor Employees, March,
1998, specifies that individuals have the
authority to stop work due to hazardous
conditions.
This stop work authority is not limited to just
radiological hazards. Workers may "stop work
when they discover employee exposures to
imminent danger conditions or other serious
hazards." Contractors are required to have
procedures addressing stop work authority.
E. Evaluation of Performance
Evaluation of performance, critiques, post job
reviews, and lessons learned are discussed in
this section.
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F. Special Applications
Section 15
This section examines the special aspects for
the control of radiological work when working
with the following:
• Plutonium
• Uranium
• Tritium
• Accelerators
• Radiation Generating Devices
G. Radiological Design Criteria
This section addresses design objectives for
design of new facilities and modification of
existing facilities.
VI. Chapter 4, Radioactive Materials
The requirements for labeling, storage, control,
release, and transportation of radioactive materials,
and the control of radioactive sources, are
discussed in this chapter. This chapter also deals
with the management of solid and liquid radioactive
wastes, and airborne radioactivity. Support activities
such as personnel protective clothing and
equipment, laundry, decontamination and vacuum
cleaners, and portable air-handling equipment are
also discussed.
VII. Chapter 5, Radiological Health Support Operations
This chapter discusses the requirements for
external dosimetry, internal dosimetry, a respiratory
protection program, the handling of contaminated
personnel, radiological monitoring and surveys, and
instrumentation and calibration.
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VIII. Chapter 6, Training and Qualification
The requirements that ensure personnel have the
training and qualifications needed to safely work in
and around radiological areas and to maintain their
own doses and those of others (ALARA) are
discussed in this chapter.
A. General Radiological Training
Within these sections, training and qualification
standards are discussed for:
• General Employees
• Radiological Workers I and II
• Radiological Control Technicians and
Supervisors
B. Other Radiological Training
This section addresses training and qualification
for:
• Managers/supervisors
• ALARA training for:
– Engineers
– Schedulers
– Procedure writers
• Radiological control personnel
– Dosimetry technicians
– Instrument technicians
– Medical personnel
– Records clerk
– Whole body counter technicians
– Laboratory personnel
• Radiographers
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• Radiation-generating device operators
• Emergency response personnel
C. Training for Special Applications
This section addresses training for the following
facilities:
• Plutonium
• Uranium
• Tritium
• Accelerators
IV. Chapter 7, Radiological Records
The requirements for employee and visitor records,
radiological control procedures (policies,
procedures, Radiological Work Permits (RWPs),
ALARA, and quality assurance records), radiological
surveys, instrumentation and calibration records,
records management, and radiological reporting are
presented in this section.
Part 4 - Student's Guide