External Dosimetry Program - Entire Document (Very Large)
G-10 CFR 835/C2 - Rev. 1
NOVEMBER 1994
IMPLEMENTATION GUIDE
For Use With Title 10, Code of Federal Regulations, Part 835
OCCUPATIONAL RADIATION PROTECTION
EXTERNAL DOSIMETRY PROGRAM
ASSISTANT SECRETARY for ENVIRONMENT, SAFETY and HEALTH
FINAL GUIDE - FOR UNLIMITED USE and DISTRIBUTION
U.S. Department of Energy IMPLEMENTATION GUIDE
G-10 CFR 835/C2 - Rev. 1
EXTERNAL DOSIMETRY PROGRAM
CONTENTS PAGE
I. PURPOSE AND APPLICABILITY . . . . . . . . . . . . . . . . . . 1
II. DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . 2
III. DISCUSSION. . . . . . . . . . . . . . . . . . . . . . . . . . 5
IV. IMPLEMENTATION GUIDANCE . . . . . . . . . . . . . . . . . . . 7
A. Guidance for Monitoring the Individual . . . . . . . . . . 8
1. Design of the External Dosimetry Program. . . . . . . . 8
2. Establishing Categories of Individuals for Monitoring . 9
3. Routine Monitoring of External Exposures. . . . . . . . 9
4. Lost, Damaged, or Contaminated Dosimetry. . . . . . . . 13
5. Nuclear Accident Dosimetry. . . . . . . . . . . . . . . 13
6. Planned Special Exposures . . . . . . . . . . . . . . . 14
B. External Dose Evaluation . . . . . . . . . . . . . . . . . 15
1. Required Dose Calculations. . . . . . . . . . . . . . . 15
2. Special Considerations. . . . . . . . . . . . . . . . . 16
3. Combining External Plus Internal Doses. . . . . . . . . 18
C. Guidance for Monitoring in the Workplace . . . . . . . . . 19
1. Performance Requirements. . . . . . . . . . . . . . . . 19
2. Allowance for Physical Characteristics. . . . . . . . . 19
3. Recourse for Technology Shortfall . . . . . . . . . . . 20
D. Recording External Doses and Related Information . . . . . 20
1. Requirements. . . . . . . . . . . . . . . . . . . . . . 20
2. Individual Information. . . . . . . . . . . . . . . . . 22
3. Dose Evaluation Information . . . . . . . . . . . . . . 22
4. Dose Evaluation Records . . . . . . . . . . . . . . . . 22
E. Reporting Requirements . . . . . . . . . . . . . . . . . . 23
F. Organization, Staffing, Training, and Facilities . . . . . 23
1. Organization. . . . . . . . . . . . . . . . . . . . . . 23
2. Staffing. . . . . . . . . . . . . . . . . . . . . . . . 24
3. Training, Experience, and Continuing Education. . . . . 24
4. Facilities and Resources. . . . . . . . . . . . . . . . 25
G. External Dosimetry Documentation . . . . . . . . . . . . . 25
1. External Dosimetry Technical Basis Document . . . . . . 25
2. Procedures. . . . . . . . . . . . . . . . . . . . . . . 25
H. Medical Response . . . . . . . . . . . . . . . . . . . . . 26
I. Quality Assurance. . . . . . . . . . . . . . . . . . . . . 26
1. General Requirement . . . . . . . . . . . . . . . . . . 26
2. Independent Review. . . . . . . . . . . . . . . . . . . 27
V. REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . . 28
VI. SUPPORTING DOCUMENTS. . . . . . . . . . . . . . . . . . . . . 28
APPENDIX
10 CFR 835, Implementation Guide, and DOE Radiological
Control Manual Cross-Reference. . . . . . . . . . . . . . . 30
Section I - Purpose and Applicability
I. PURPOSE AND APPLICABILITY
This Implementation Guide (IG) provides an acceptable methodology for
establishing and operating an external dosimetry program that will
comply with U.S. Department of Energy (DOE) requirements specified in
Title 10 of the Code of Federal Regulations (CFR), Part 835,
"Occupational Radiation Protection" (DOE, 1993a); hereinafter referred to
as 10 CFR 835. For completeness, this IG also identifies applicable
requirements and recommendations contained in DOE Order 5480.11, as
amended, "Radiation Protection for Occupational Workers" (DOE, 1992),
DOE's "Radiological Control Manual" (DOE, 1994a); hereinafter referred to
as the RCM)(with the associated numbers denoting the article numbers),
and secondary documents (American National Standards Institute (ANSI)
Standards, etc.) invoked by these and other primary documents. The
Appendix of this IG provides a cross-reference of the applicable
material in 10 CFR 835, this IG, and the RCM. This IG amplifies the
regulatory requirements of 10 CFR 835, which are enforceable under the
provisions of Sections 223(c) and 234A of the Atomic Energy Act of 1954,
as amended (AEC, 1954). The requirements and recommendations of the
other DOE documents are enforceable through contractual or
administrative means.
This IG also provides guidance for the structure, function, and
operations of an external dosimetry program. The criteria for external
dosimetry programs to serve epidemiology, risk assessment, and
litigation are not within the scope of this IG.
Except for requirements mandated by a regulation, a contract, or by
administrative means, the provisions in this IG are DOE's views on
acceptable methods of program implementation and are not mandatory.
Conformance with this guide will, however, create an inference of
compliance with the related regulatory requirements. Alternate methods
that are demonstrated to provide an equivalent or better level of
protection are acceptable. Contractors are encouraged to go beyond the
minimum requirements and to pursue excellence in their programs.
The word "shall" is used in this IG to designate requirements from 10
CFR 835, DOE Orders, the RCM, and secondary documents invoked by them.
The requirements of 10 CFR 835 are mandatory except to the extent an
exemption has been granted pursuant to 10 CFR 820, "Procedural Rules for
DOE Nuclear Activities" (DOE, 1993b) and are identified by a bolded and
underlined "shall."
Requirements taken from DOE Orders and the RCM are mandatory to the extent
they are invoked by a contract or through administrative means.
Those facilities not subject to the requirements of 10 CFR 835 should
substitute the corresponding DOE 5480.11 requirements.
This IG is applicable to all DOE activities involving occupational
exposure to ionizing radiation of DOE employees and/or
DOE-contractor/subcontractor employees.
Section II - Definitions
II. DEFINITIONS
absorbed dose (D): The energy absorbed by matter from 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).
calibration: To adjust and/or determine either:
(i) the response or reading of an instrument relative to a
standard or to a series of conventionally true values; or
(ii) the strength of a radiation source relative to a standard or
conventionally true value.
committed dose equivalent (Ht,50): The dose equivalent calculated to be
received by a tissue or organ over a 50-year period after the intake of
a radionuclide into the body. It does not include contributions from
radiation sources external to the body. Committed dose equivalent is
expressed in units of rem (or sievert).
committed effective dose equivalent (He,50): The sum of the committed
dose equivalents to various tissues in the body (Ht,50), each multiplied
by the appropriate weighting factor (wT) -- that is, He,50 = sum(wT*Ht,50).
Committed effective dose equivalent is expressed in units of rem (or
sievert).
controlled area: Any area to which access is managed in order to
protect individuals from exposure to radiation and/or radioactive
materials.
cumulative total effective dose equivalent: The sum of the total
effective dose equivalents recorded for an individual for each year of
employment at a DOE or DOE contractor site or facility, effective
January 1, 1989.
declared pregnant worker: A woman who has voluntarily declared to her
employer, in writing, her pregnancy for the purpose of being subject to
the occupational exposure limits to the embryo/fetus as provided in 10
CFR 835.206. This declaration may be revoked, in writing, at any time
by the declared pregnant worker.
deep dose equivalent: The dose equivalent derived from external
radiation at a depth of 1 cm in tissue.
DOELAP: The Department of Energy Laboratory Accreditation Program for
personnel dosimetry under DOE Order 5480.15.
dose equivalent (H): The product of absorbed dose (D) in rads (or gray)
in tissue, a quality factor (Q), and other modifying factors (N). Dose
equivalent is expressed in units of rem (or sievert) (1 rem = 0.01
sievert).
effective dose equivalent (He): The summation of the products of the
dose equivalent received by specified tissues of the body (Ht) and the
appropriate weighting factor (wT) -- that is, He = sum(wT*Ht). It includes
the dose from radiation sources internal and/or external to the body.
The effective dose equivalent is expressed in units of rem (or sievert).
exposure: The general condition of being subjected to ionizing
radiation, such as by exposure to ionizing radiation from external
sources or to ionizing radiation sources inside the body. In this
document, exposure does not refer to the radiological physics concept of
charge liberated per unit mass of air.
external dose or exposure: That portion of the dose equivalent received
from radiation sources (e.g., "external sources") outside the body.
extremity: Hands and arms below the elbow or feet and legs below the
knee.
general employee: An individual who is either a DOE or DOE-contractor
employee; an employee of a subcontractor to a DOE-contractor; or a
visitor who performs work for, or in conjunction with, DOE or utilizes
DOE facilities.
gray (Gy): System International (SI) unit of absorbed dose. One gray
is equal to an absorbed dose of 1 joule per kilogram (100 rads).
high radiation area: Any area, accessible to individuals, in which
radiation levels could result in an individual receiving a deep dose
equivalent in excess of 0.1 rem (0.001 sievert) in 1 hour at 30 cm from
the radiation source or from any surface that the radiation penetrates.
lens of the eye dose equivalent: The external exposure of the lens of
the eye taken as the dose equivalent at a tissue depth of 0.3 cm.
lifetime control level: An administrative value used to limit a
worker's lifetime occupational radiation dose. The lifetime control
level is equal to N times 1 rem (N times 0.01 sievert), where N is the
age of the worker in years.
lifetime occupational dose: The sum of all occupational total effective
dose equivalent values for each year since January 1, 1989, plus the sum
of occupational external dose equivalent (or deep dose equivalent)
values and occupational internal effective dose equivalent values prior
to January 1, 1989.
member of the public: An individual who is not occupationally exposed
to radiation or radioactive material. An individual is not a "member of
the public" during any period in which the individual receives
occupational exposure.
minor: An individual less than 18 years of age.
monitoring: Actions intended to detect and quantify radiological
conditions.
nonstochastic effects: Effects due to radiation exposure for which the
severity varies with the dose and for which a threshold normally exists
(e.g., radiation-induced opacities within the lens of the eye). Also
called deterministic effects.
occupational exposure: An individual's exposure to ionizing radiation
(external and internal) as a result of that individual's work
assignment. Occupational exposure does not include planned special
exposures, exposure received as a medical patient, background radiation,
or voluntary participation in medical research programs.
quality factor: The principal modifying factor used to calculate the
dose equivalent from the absorbed dose; the absorbed dose (expressed in
rad or gray) is multiplied by the appropriate quality factor (Q). The
quality factors to be used for determining dose equivalent in rem are
provided in 10 CFR 835. radiation area: Any area accessible to
individuals in which radiation levels could result in an individual
receiving a deep dose equivalent in excess of 0.005 rem (0.05
millisievert) in one hour at 30 centi-meters from the source or from any
surface that the radiation penetrates.
radiological area: Any area within a controlled area which must be posted
as a "radiation area," "high radiation area," "very high radiation area,"
"contamination area," "high contamination area," or "airborne radioactivity
area" in accordance with 10 CFR 835.603.
radiological buffer area (RBA): Any inter-mediate area established to
prevent the spread of radioactive contamination and to protect personnel
from radiation exposure.
radiological worker: A general employee whose job assignment involves
operation of radiation producing devices or working with radioactive
materials, or who is likely to be routinely occupationally exposed above
0.1 rem (0.001 Sv).
shall: Within the context of this Guide, the word "shall" is used to
designate requirements from regulations, DOE Orders, the RCM, and
secondary documents invoked by them.
shallow dose equivalent: The dose equivalent derived from external
radiation at a depth of 0.007 cm in tissue.
should and may: Within the context of this Guide, the words "should"
and "may" are used to represent optional program recommendations and
allowable alternatives, respectively. Deviations generally require no
specific approval or justification; however exceptions or deviations to
"should" provisions referenced directly from the RCM require specific
justification and approval in accordance with Article 113.3 of that
manual (i.e., RCM 113.3).
sievert (Sv): The SI unit of any of the quantities expressed as dose
equivalent. (The dose equivalent in sieverts is equal to the absorbed
dose in grays multiplied by the quality factor (1 Sv = 100 rem)).
stochastic effects: Malignant and hereditary diseases for which the
probability of an effect occurring, rather than its severity, is
regarded as a function of dose without a threshold for radiation
protection purposes.
total effective dose equivalent (TEDE): The sum of the effective dose
equivalent (for external exposures) and the committed effective dose
equivalent (for internal exposures). For purposes of compliance, deep
dose equivalent to the whole body may be used as effective dose
equivalent for external exposures. ( Note that the TEDE does not
include the committed effective dose equivalent contributions from
intakes in prior years.)
uniform exposure: Hypothetical radiation field in which the fluence and
its angular and energy distributions are the same throughout the volume
of interest.
very high radiation area: Any area accessible to individuals in which
radiation levels could result in an individual receiving an absorbed
dose in excess of 500 rads (5 grays) in one hour at 1 meter from a
radiation source or from any surface that the radiation penetrates.
weighting factor (wT): The fraction of the overall health risk,
resulting from uniform, whole body irradiation, attributable to a
specific tissue (T). The dose equivalent to tissue, T, is multiplied by
the appropriate weighting factor and summed to obtain the effective dose
equivalent to the whole body. The weighting factors are provided in 10
CFR 835.
whole body: For the purposes of external exposure, head, trunk
(including male gonads), arms above and including the elbow, or legs
above and including the knee.
workplace monitoring: The measurement of radioactive material and/or
direct radiation levels in areas that could be routinely occupied by
workers.
Section III - Discussion
III. DISCUSSION
External dosimetry is the science dealing with measurement of a
radiation field incident to the body and the evaluation of the dose
equivalent resulting from energy deposited within the body by the
radiation. External dose is usually a derived or inferred quantity
since it is not possible to directly measure the exact dose to any organ
or tissue. Any measurement must be compared to a known quantity to
derive dose and dose equivalent.
10 CFR 835 contains requirements which affect external dosimetry
programs through-out DOE and DOE-contractor facilities. The salient
features are:
-- External dose equivalent to workers "shall" be computed and recorded
when monitored in accordance with 10 CFR 835.402(a) & 702(a) (also
RCM 722.4);
-- internal doses shall be added to external doses for the purposes of
demonstrating compliance with occupational dose limits and keeping
worker doses "as low as reasonably achievable" (ALARA)(10 CFR
835.703(a)). The quantity, total effective dose equivalent, is the
result of a methodology by which internal doses are added to
external doses on the basis of equal risk; and
-- monitoring in the workplace "shall" be routinely performed, as
necessary, to identify and control potential sources of radiation
exposures (10 CFR 835.401(b)) (also RCM 514.1, 514.3, 551.1 &
552.2).
10 CFR 835 states that the occupational exposure of general employees to
radiation or radioactive material resulting from routine DOE nuclear and
radiation activities "shall" not cause the following annual limits to be
exceeded: (1) A total effective dose equivalent from both internal and
external sources of 5 rems (0.05 Sv); (2) the sum of the dose equivalent
for external exposures and the committed dose equivalent to any organ
other than the lens of the eye of 50 rems (0.5 Sv); (3) a lens of the
eye dose equivalent of 15 rem (0.15 Sv); and (4) a shallow dose
equivalent of 50 rem ((0.5 Sv) to the skin or any extremity (10 CFR
835.202(a) and RCM 213.1 & Table 2-1). Note that Subpart N of 10 CFR
835 contains provisions for accidents and emergencies. These
requirements are not discussed in this IG with the exception that
Section IV.A.5. of this IG does briefly discusses nuclear accident
dosimetry.
Several limits other than those for general employees must be considered
in the design of an external dosimetry program. A limit of 0.5 rem
(0.005 Sv) dose equivalent for the period from conception to birth for
the embryo/fetus of a declared pregnant worker "shall" not be exceeded
and efforts "shall" be made to avoid substantial variation above a uniform
exposure rate that would satisfy the limit (i.e., 50 mrem (0.5 mSv) per
month to the declared pregnant worker)(10 CFR 835.206(a) & (b) and RCM
215 & Table 2-1). An annual limit of 0.1 rem (0.001 Sv) total
effective dose equivalent for minors accessing a DOE site or facility
(10 CFR 835.207 and RCM Table 2-1), members of the public entering a
controlled area (10 CFR 835.208 and RCM Table 2-1), and visitors (RCM
Table 2-1 and RCM 214) "shall" not be exceeded. All occupational exposure
received during the current year "shall" be included when demonstrating
compliance with the annual limits (10 CFR 835.202(b) and RCM 213.1).
Occupational dose evaluation and dose records "shall" not include
exposures from background, therapeutic and diag-nostic medical
radiation, and voluntary participation in medical research programs (10
CFR 835.202(c) and RCM Table 2-1, Note 3).
The RCM introduces additional controls:
-- Administrative control levels which are below dose limits of the
RCM and 10 CFR 835 (RCM 211);
-- the lifetime control level of N rem, where N is the individual's
age in years (RCM 212); and
-- special control levels for individualized exposure control (RCM
216).
The RCM establishes a DOE administrative control level of 2 rems (0.02
Sv) per year per person for all DOE activities and requires the
establishment of a facility administrative control level that is less
than the DOE administrative control level (RCM 211). The administrative
control levels apply to the total effective dose equivalent. The
lifetime control level applies to lifetime occupational radiation dose
which is the sum of all total effective dose equivalent values for each
year since January 1, 1989, plus the sum of external dose equivalent (or
deep dose equivalent) values and internal effective dose equivalent
values recorded prior to January 1, 1989. Special control levels apply
to total effective dose equivalent values and shall be established for
individuals who have a lifetime occupational dose, in rem, that exceeds
their age in years (RCM 216.1). Special control levels should be
considered for persons undergoing radiation therapy.
Radiation protection programs for limiting external exposures are based
on the DOE policy that administrative and engineering controls and
shielding material should be used to the extent reasonably achievable,
so that personnel are not exposed unnecessarily. It is nonetheless
recognized that low-level, chronic occupational exposures to external
ionizing radiation are difficult to avoid at some facilities, due to the
types of material handled or processed necessitating an external
dosimetry program at most DOE and DOE-contractor facilities.
10 CFR 835 was written to implement radiation protection standards that
are consistent with the Presidential approved guidance to Federal
Agencies, promulgated by the Environmental Protection Agency "Radiation
Protection Guidance to Federal Agencies for Occupational Exposure -
Recommendations Approved by the President" (EPA, 1987). It reflects many
of the scientific recommendations of the National Council on Radiation
Protection and Measurements (NCRP) and the International Commission on
Radiological Protection (ICRP). 10 CFR 835 contains primary limits for
exposure of workers to internal and external sources of ionizing
radiation and control of radiological conditions in the work place. The
primary annual limits are expressed in terms of total effective dose
equivalent (TEDE) to the whole body, lens of the eye dose equivalent,
shallow dose equivalent to any extremity or to the skin, and the sum of
the dose equivalent for external exposures and the committed dose
equivalent for internal exposures to any other individual organs or
tissues.
Personnel dosimeter measurements and associated external dose
evaluations are the primary method for demonstrating compliance with the
external component of dose limits for protecting workers. These
measurement systems shall also comply with the requirements of the
"Department of Energy Laboratory Accreditation Program for Personnel
Dosimetry" (DOELAP) (DOE, 1988a). (Extremity dosimeters are currently not
covered by an accreditation program.) In addition to individual dose
evaluations, collective dose, average worker dose, and maximum dose to a
worker should be determined and used to track the perform-ance of the
radiation protection program. Both area radiation monitoring and
personnel dosimeter results "shall" be used by a facility's radiation
protection organization to manage worker exposures to maintain them
below the limits and ALARA (10 CFR 835.1003(b) and RCM 511.1, 514.1 &
551.1).
Section IV - Introduction
IV. IMPLEMENTATION GUIDANCE
This section provides basic guidance for conducting external dosimetry
programs for workers who are likely to receive external exposure to
ionizing radiation. Conducting an external dosimetry program involves
determining monitoring methods, frequency, distribution and control, and
evaluating external dose from monitoring results. This section also
includes guidance for conducting workplace monitoring of external
radiation, and for recording, reporting, and managing external doses.
Organization, staffing, and training, as well as the requirement for an
External Dosimetry Technical Basis Document, are also addressed in this
section.
The essential elements of an acceptable external dosimetry program are
as follows:
-- Adequate staff shall be maintained and shall be provided with
appropriate technical training (RCM 121.2, 651, 652, and 654);
-- a technical basis document shall be developed and maintained giving
scientific information and other rationale explaining each element
of the external dosimetry program (RCM 512.1);
-- complete historical records of personnel dosimeter measurement
results and dose assessments "shall" be maintained (10 CFR 835.702(a)
& 703(b) and RCM 722, 751 & 752); and
-- an internal audit program "shall" be conducted no less frequently
than every 3 years (10 CFR 835.102 and RCM 134.1).
In addition, an external dosimetry program should contain the following
elements:
-- Written policies and procedures covering each step in the
activities that determine worker external dose;
-- appropriate personnel dosimeter measurement methods and
frequencies;
-- adequate detection capability and quality of personnel dosimeter
measurements;
-- appropriate dosimetric models and default parameters for evaluating
external dose;
-- methods for control, accountability, and safe handling of
dosimeters;
-- appropriate action level and investigation level guidelines;
-- timely analysis of personnel dosimeter measurements, transmission
of results, dose evaluation, and recommendations to management;
-- historical records of the external dosimetry program and
procedures, as well as changes in the programs and procedures;
-- quality assurance program covering all steps in the activities that
determine worker external dose;
-- appropriate workplace monitoring program;
-- criteria for identifying individuals who need to be monitored for
exposure to external sources of radiation; and
-- a program to report external doses to workers, management, and DOE.
Unless otherwise specified, the quantities used in the records required
by 10 CFR 835 "shall" be clearly indicated in special units of curie, rad,
or rem, including multiples and subdivisions of these units. The
System International (SI) units, becquerel (Bq), gray (Gy), and sievert
(Sv), are only provided parenthetically in 10 CFR 835 and this guide for
reference with scientific standards (10 CFR 835.4).
Section IV, Subsection A - Guidance for Monitoring the Individual
A. Guidance for Monitoring the Individual
10 CFR 835.402(a) requires that monitoring of individual exposures to
external radiation "shall" be performed in accordance with the following:
(1) Personnel dosimeters "shall" be provided to and used by radiological
workers who, under typical conditions, are likely to receive an
effective dose equivalent to the whole body of 0.1 rem (0.001 Sv) or
more in a year; a shallow dose equivalent to the skin or to any
extremity of 5 rems (0.05 Sv) or more in a year; a dose equivalent to
the lens of the eye of 1.5 rems (0.015 Sv) or more in a year; a deep
dose equivalent from external exposure to any organ or tissue other than
the lens of the eye of 5 rems (0.05 Sv) or more in a year; and (2)
personnel external dosimetry programs "shall" be adequate to demonstrate
compliance with 10 CFR 835.202, including routine dosimeter calibration
and conformance with the requirements of the DOE Laboratory
Accreditation Program for Personnel Dosimetry (10 CFR 835.402(b) and RCM
511.1.a). The specific requirements of DOELAP may be found in DOE Order
5480.15, "Department of Energy Laboratory Accreditation Program for
Personnel Dosimetry" (DOE, 1988a).
Declared pregnant workers who are likely to receive a dose equivalent
greater than 50 mrems (0.5 mSv) to the embryo/fetus from external
sources "shall" be monitored (10 CFR 835.402(a)(2) and RCM 511.1.b).
Minors and members of the public who are likely to receive greater than
50 mrems (0.5 mSv) in 1 year from external sources and individuals
entering a high or very high radiation area shall also be monitored (10
CFR 835.402(a)(3 & 4) and RCM 334.3, 334.4 & 511.1.c). When personnel
dosimeters are provided, the exposure "shall" be evaluated and recorded
for each monitoring period (10 CFR 835.702(a) & (b) and RCM 722.1).
1. Design of the External Dosimetry Program
Individual monitoring programs "shall" be designed and conducted to
evaluate the dose equivalent to an individual in order to:
-- Demonstrate compliance with the dose limits of 10 CFR 835 (and the
RCM);
-- document radiological conditions in the workplace;
-- detect changes in radiological conditions;
-- detect the gradual buildup of radioactive material in the
workplace; and
-- verify the effectiveness of engineering and process controls in
containing radioactive material and reducing radiation exposure (10
CFR 835.401(a) and RCM 511.1, 514.1, 514.3, 551.1, 551.7 & 551.8).
The individual monitoring program should also provide data for the ALARA
program.
The routine personnel dosimeter monitoring interval depends on the
measurement method and associated lower limit of detectability. The
monitoring interval should be chosen so that it is unlikely that an
individual will receive a dose equal to or greater than the dose
quantities listed in 10 CFR 835.402 in a year from external radiation
without detection. Personnel monitoring methods, their lower limits of
detectability, and monitoring intervals should be specified in the
external dosimetry technical basis document, along with a rationale or
justification for the methods and intervals chosen.
To ensure that the monitoring requirements of 10 CFR 835.402 and RCM 511.1
are met, the external dosimetry program should be capable of evaluating
external exposures to ionizing radiation that deliver an effective dose
equivalent of 50 mrems (0.5 mSv) or more in any 12-month period. The 50
mrems (0.5 mSv) value is the most restrictive monitoring threshold and
applies to the embryo/fetus of declared pregnant workers, minors, students,
visitors, and members of the public.
The specific physical characteristics of the radiation field in the
workplace should be taken into account in choosing the measurement
method for evaluation of external dose. These characteristics include
such things as radiation quality, energy, fluence rate, and direction of
incidence. If these characteristics are not quantified, conservative
assumptions should be used until further information is available, and
should be stated in the external dosimetry technical basis document.
If the performance objective cannot be achieved because of shortfalls in
available dosimetry technology, the facility should: (1) Use the best
practicable (state-of-the-art) dosimetry methods, and (2) implement
enhanced design, operation, controls, and personnel protection equipment
and procedures to minimize external exposures.
2. Establishing Categories of Individuals for Monitoring
It is not necessary for all individuals at a facility to wear dosimeters
unless there is a documented technical basis. Unnecessary issuance of
dosimeters should be avoided (RCM 511.4). If a person does not enter a
radiation area, high radiation area, or very high radiation area, the
potential for external exposure should be evaluated before issuing that
person a dosimeter. The issuance of dosimeters to concerned individuals
should not be a substitute for providing information and training. The
criteria for the selection of individuals to be monitored should be
documented in the External Dosimetry Technical Basis Document, as
described in Section IV.G.1. of this guide.
Dosimeters shall only be issued to individuals who have been formally
instructed in their use and shall be worn only by those to whom the
dosimeters were issued (RCM 511.2). For visitors needing access to
controlled areas, the formal instruction requirement can be accomplished
by a radiological orientation handout that is read and signed by the
visitor (RCM 622).
3. Routine Monitoring of External Exposures
The distribution and control of individual dosimeters should take into
consideration the geographical layout of the site and radiological
facilities and worker populations. The practice of taking
thermoluminescent dosimeters off-site is discouraged and film dosimeters
shall not be taken or worn off-site unless specifically authorized by
the radiation protection manager (RCM 511.7 & 8). Individual dosimeters
issued at one site shall not be worn at another site when dosimeters are
also issued for the other site. Personnel shall not expose their
dosimeters to X-ray devices, excessive heat or sunlight, or medical
sources of radiation (RCM 511.9).
a. Whole Body Dosimetry
The effective dose equivalent from external exposures should be taken as
the deep dose equivalent to the whole body measured at a tissue depth of
1 cm (1000 mg/cm2) and measured at the maximally exposed portion of the
whole body. If another method is used to estimate the effective dose
equivalent, such as described in Section IV.B.2. of this guide, the
rationale for using the alternate method should be documented in the
External Dosimetry Technical Basis Document.
External dose is typically determined using such individual monitoring
devices as thermoluminescent dosimeters, track etch dosimeters, and
radiation sensitive film. The dosimeter should be worn so as to provide a
measurement of the maximum exposure received at any location on the whole
body. When the whole body is exposed fairly uniformly, the location should
be on the front of the torso between the neck and waist (RCM 511.6). For
nonuniform irradiation where the cumulative doses vary by more than 50%
over the torso, see Section IV.A.3.d of this IG for guidance on the use of
multiple dosimeters.
Whole body monitoring "shall" be performed when a radiological worker is
likely to exceed an effective dose equivalent of 100 mrems (1 mSv) or
more in a year (10 CFR 835.402(a)(1)(i) and RCM 511.1.a), when a minor
or member of the public is likely to receive 50 mrems (0.05 mSv) or more
in a year (10 CFR 835.402(a)(3) and RCM 511.1.c), when a declared
pregnant worker is likely to exceed 50 mrems (0.05 Sv) during the entire
gestation period (10 CFR 835.402(a)(2) and RCM 511.1.b), or when an
individual enters a high or very high radiation area (10 CFR
835.402(a)(4) and RCM 334.3-4). The RCM also requires that neutron
dosimetry be provided when a person is likely to exceed 100 mrems (1
mSv) annually from neutrons (RCM 511.2). In addition, external
monitoring is required for any unescorted individual entering a
Radiation Area (RCM 334.1). Surveys of exposure rates and estimates of
occupancy times may be used to evaluate expected external doses. The
potential for unlikely exposures and accident conditions need not be
considered when determining who to monitor because these events, by
definition, are not likely, except that nuclear accident dosimetry "shall"
be used in those cases where sufficient quantities of fissile material
exist to potentially constitute a critical mass such that the excessive
exposure of personnel to radiation from a nuclear accident is possible
(10 CFR 835.1304 and RCM 515).
Exposure to the skin from external radiation, not including skin
contamination incidents as discussed in Section IV.B.2 of this IG) "shall"
be evaluated using the shallow dose equivalent as measured at a tissue
depth of 0.007 cm (7 mg/cm2)(10 CFR 835.2(b)). Monitoring "shall" be
performed if a worker is likely to receive a shallow dose equivalent to
the skin of 5 rems (0.05 Sv) or more in a year (10 CFR 835.402(a)(1)(ii)
and RCM 511.1.a). The measurement for skin exposure is usually
performed in conjunction with measuring the deep dose equivalent using a
single whole body dosimeter. This method is adequate for uniform or
nearly uniform fields.
DOELAP accreditation of dosimeters is required for the type(s) of
radiation that most closely approximates the type(s) for which the
individual is being monitored. The use and evaluation of whole body
dosimeters outside the scope of DOELAP, such as high energy accelerator
dosimeters, shall be addressed in the external dosimetry technical basis
document (RCM 512.2). National Institute of Standards and Technology
(NIST) traceable sources and secondary standards (national or
international) should be used for the calibration of all personnel
dosimeters. External dosimetry programs should participate in
intercomparison studies (RCM 512.3).
b. Lens of the Eye Dosimetry
The lens of the eye dose equivalent "shall" be measured at a tissue depth
of 0.3 cm (300 mg/cm2) (10 CFR 835.2(b)). Monitoring "shall" be performed
for any worker who is likely to receive a dose equivalent to the lens of
the eye of 1.5 rems (0.015 Sv) or more in a year (10 CFR
835.402(a)(1)(iii) and RCM 511.1.a). For uniform exposures, a
measurement taken in the torso region is sufficient. For nonuniform
exposures, such as work around reactor beams, X-ray machines, sources of
beta radiation, and penetrations in shields, the dose equivalent should
be measured near the eye, such as with a dosimeter worn on the side of
the head or forehead. When monitored, the dose equivalent to the lens
of the eye "shall" be recorded and reported separately (10 CFR 835.702(a &
b) & 801(a) and RCM 512.4, 722.4 & 781.1).
For beta particles with maximum energies less than about 3.5 MeV, the
dose limit to the skin is more restrictive than that for the lens of the
eye. At higher energies, the lens of the eye dose limit dominates.
Therefore, at beta energies below 3.5 MeV, if it can be shown that skin
monitoring is not required, then it follows that lens of the eye
monitoring is also not required (See ICRU Report No. 43, "Determination
of Dose Equivalents from External Sources - Part 2" (ICRU, 1988)). To
provide protection for the lens of the eye, use of a 1/10-inch of
acrylic plastic will completely attenuate all beta particles with
maximum energies below 800 keV. This covers most beta-emitting isotopes
with the exception of 32P, 90Y, and 234Pa (See the "Radiological Health
Handbook" (BRH, 1970)).
c. Embryo/Fetal Dosimetry
As soon as a female worker has declared her pregnancy, her dosimeter
should be taken and processed, and a dose evaluation performed to
determine the dose from the estimated time of conception to the time of
declaration. Dosimetry "shall" be provided to declared pregnant workers
who are likely to receive a dose equivalent to the embryo/ fetus in
excess of 50 mrems (0.5 mSv) from external radiation (10 CFR
835.402(a)(2) and RCM 511.1.b). If the declared pregnant worker chooses
to continue as a radiological worker and is likely to approach 50 mrems
(0.5 mSv) per month over the entire gestation period, a supplemental
dosimeter should also be provided. The supplemental dosimeter can be
either a self-reading dosimeter or a second personnel whole body
dosimeter. This supplemental dosimeter should be used to obtain a
monthly estimate of the dose to the embryo/fetus, while retaining the
primary personnel dosimeter for determining the dose of record. A
supplemental dosimeter may also be provided to a pregnant worker who
expresses concern over possible exposure to the embryo/fetus.
Dosimeters are not necessary for declared pregnant workers who are
temporarily assigned to duties that do not involve the likelihood of
exposure to radiation.
The dosimeter exchange frequency for the declared pregnant worker should
be based on the expected monthly exposure. The dosimeter may be worn
between the neck and the waist, but should be close to the waist or
abdomen if work is around localized sources of external radiation. For
further guidance on monitoring, see the IG, "Evaluation and Control of
Fetal Exposure, G-10 CFR 835/C4" (DOE, 1994b).
d. Use of Multiple Dosimeters
Multiple dosimeters should be used to assess whole body exposure when
radiation fields vary by more than 50% over the area of the whole body
and the anticipated dose is greater than 100 mrems (1mSv) (RCM 512.5).
Preliminary judgements on the need for multiple dosimeters and the
placement of multiple dosimeters can be made from direct dose rate
surveys with portable survey instruments or surveys with dosimetry
placed on phantoms. Multiple dosimeters may be used at any time to
provide more accurate estimates of whole body dose equivalent, or at the
discretion of radiation protection personnel.
Multiple dosimeters should be placed at locations on the body with the
potential of receiving the highest dose equivalent. Common locations for
placement of multiple dosimeters include the head, chest, back, gonads,
top of arms, and top of legs. If multiple dosimeters are used, the
routine whole body dosimeter should be replaced with the set of multiple
dosimeters during the multibadging activity. This keeps the normal
dosimetry on its regular processing cycle and eliminates the possibility
of "double counting" dosimetry results.
It should be noted that this guidance is for whole body dosimetersw only --
this does not apply to extremity dosimetry which is treated separately in
this IG.
e. Extremity Dosimetry
As required by 10 CFR 835 and the RCM, exposure to the skin of the
extremities is limited to 50 rems (0.5 Sv) per year to prevent
nonstochastic effects. Monitoring "shall" be performed if the
radiological worker is likely to receive a shallow dose equivalent to
the skin or any extremity of 5 rems (0.05 Sv) or more in a year (10 CFR
835.402(a)(1)(ii) and RCM 511.1.a). Only external exposure is
considered in evaluating extremity dose.
The extremity dose "shall" be the shallow dose equivalent at a tissue
depth of 0.007 cm (7 mg/cm2) (10 CFR 835.2(b)). This approach is most
consistent with the radiobiological significance of exposure to the
extremities. Those locations on the extremities experienc-ing doses
above the annual limit are most likely to be the ones expected to show
occurrence of nonstochastic effects. If the most exposed location is
not directly monitored, a field correction factor may be applied based
on a measurement of the gradient between the location monitored and the
most exposed location (or the dose equivalent at contact if there is
direct source-to-extremity contact).
Personnel extremity dosimeters should be tested against the performance
criteria contained in a draft ANSI extremity standard when published.
This requires a one time char- acterization of the dosimeter's angular
response and lower limit of detectability as well as accuracy and
precision measurements for different categories of sources.
The justification for the choice of extremity dosimeter, placement of
dosimeter, and results of field gradient measurements should be
contained in the external dosimetry technical basis document. The
results of extremity dosimeter performance testing against the draft
ANSI standard should also be recorded in the external dosimetry
technical basis document.
f. Supplemental Dosimetry
The RCM lists requirements covering the use of supplemental dosimeters
(RCM 513). Supplemental dosimeters include, but are not limited to,
electronic dosimeters, pocket dosimeters, and other self-reading,
alarming dosimeters. Supplemental dosimeters are required for any
individual entering a high radiation area or a very high radiation area,
when a person could exceed 10% of an administrative control level from
external radiation in one work day, or when required by a radiological
work permit (RCM 513.1). The RCM also requires that supplemental
dosimeters be worn simultaneously with the primary dosimeter and in the
proper location (RCM 513.2), and be read periodically while in use (RCM
513.3). The range and energy dependence of supplemental dosimeters,
particularly to low-energy beta and X-ray radiation, should be
considered in determining their applicability (RCM 513.5). Supplemental
dosimeters with a limited range should be selected with the lowest range
applicable for the anticipated exposure (RCM 513.1). Supplemental
dosimeters should be tested against the performance specifications given
in ANSI N13.5, "Performance Specifications for Direct Reading and
Indirect Reading Pocket Dosimeters for X- and Gamma Radiation" (ANSI,
1989a) and ANSI N13.27, "Performance Requirements for Pocket-Sized Alarm
Dosimeters and Alarm Rate Meters" (ANSI, 1992) and the results
documented in the External Dosimetry Technical Basis Document.
4. Lost, Damaged, or Contaminated Dosimetry
A person whose dosimeter is lost, damaged, or contaminated should place
work in a safe condition, immediately exit the area, and report the
occurrence to the radiation protection organization (RCM 511.10). A
person may suspect his/her dosimeter has become contaminated if the
plastic bag or pouch that contains the dosimeter is torn or punctured
while working in a contaminated or airborne radioactive material area.
Dosimeters should always be surveyed for contamination prior to exiting
contamination, high contamination, or airborne radioactivity areas.
Reentry of the person into a radiological areas should not be made until
a review has been conducted, the person has been issued a new dosimeter,
and management has approved reentry (RCM 511.10). The review may be as
simple as a documented survey showing the dosimeter not to be
contaminated, in which case the worker may go back to work immediately.
Otherwise, a review shall include a dose evaluation to replace the
results of the lost, damaged, or contaminated dosimeter (RCM 512), and
should determine if work can continue while an investigation is in
progress. The number of dose evaluations for lost, damaged, or
contaminated dosimeters should be used as a performance indicator for
the distribution and control elements of the individual monitoring
program.
5. Nuclear Accident Dosimetry
A nuclear accident dosimetry program "shall" be implemented when
sufficient quantities and kinds of fissile material exist to potentially
constitute a critical mass as defined in DOE Order 5480.5, "Safety of
Nuclear Facilities" (DOE, 1987a) and where excessive exposure of
personnel to radiation from a nuclear accident is possible (10 CFR
835.1304(a) and RCM 515). The nuclear accident dosimetry program "shall"
include a method to conduct initial screening of personnel involved in a
nuclear accident to determine whether significant exposure to radiation
and/or contamination occured, methods and equipment for analysis of
biological materials, and a system of fixed nuclear accident dosimeter
units (10 CFR 835.1304(b)(1),(2),(3)). All personnel who enter any area
requiring an installed criticality alarm system shall wear personal
nuclear accident dosimeters (10 CFR 835.1304(b)(4)).
DOE Order 5480.11(9)(q)(1)(b) also requires that counting facilities be
available to evaluate fixed and/or personnel dosimeters, sodium-24
activity in blood, and phosphorous-32 activity in hair.
DOE Order 5480.11(9)(q)(2) requires that the system of fixed nuclear
accident dosimeter units be capable of yielding estimated radiation dose
and the approximate neutron spectrum at their locations within the
following performance criteria:
-- The fixed unit shall be capable of determining neutron dose in rad
(gray) with an accuracy of +- 25%;
-- the fixed unit shall be capable of providing the approximate
neutron spectrum to permit the conversion of rad to rem;
-- the fixed unit's neutron component dose range capability shall
extend from 10 rads (0.1 gray) to about 10,000 rads (100 grays);
-- the fixed unit's gamma ray component shall be capable of measuring
fission gamma radiation in the presence of neutrons with an
accuracy of approximately +-20%; and
-- the gamma component dose range capability shall extend from 10
rems(0.1 sievert) to about 10,000 rems(100 sieverts).
The number of fixed nuclear accident dosimeter units, their locations, the
effect of intervening shielding, and an analysis demonstrating the above
performance criteria should be documented in the External Dosimetry
Technical Basis Document. The placement of fixed nuclear accident
dosimeter units should take into account the nature of the operations,
structural design characteristics, accessibility of areas to personnel, and
recovery of units after a criticality accident.
Personal nuclear accident dosimeters should be capable of determining
gamma dose from 10 rads (0.1 gray) to 1,000 rads (10 grays) with an
accuracy of +-20% and neutron dose from 1 rad (0.01 gray) to 1,000 rads
(10 grays) with an accuracy of +-25% without dependence upon fixed
nuclear accident dosimeter data.
Currently there are no provisions for the exclusion of doses from
accidents from controlling future occupational doses. There are
provisions in 10 CFR 835 for the exclusion of doses received from
planned special exposures and emergency situations from controlling
future occupational doses. These provisions allow for individuals to
respond to emergency or unusual situations without the dose received
during these actions being counted towards any occupational limits.
Therefore doses received in response to emergency or unusual situations
will not impact the responder's future work activities in any manner.
Doses from accidents do not meet this intent and should be included with
occupational doses. Subpart N of 10 CFR 835 provides guidance on
permitting individuals who have occupational exposures in excess of the
limits to return to work in radiological areas.
6. Planned Special Exposures
A planned special exposure may be necessary, during normal operations,
where an individual is permitted to receive an exposure in excess of the
annual occupational dose limits. The planned special exposure "shall" be
controlled such that the contribution from all planned special exposures
for an individual does not exceed a total effective dose equivalent of 5
rems (0.05 Sv) in a year and a cumulative TEDE of 25 rems (0.25 Sv) (10
CFR 835.204(c) and RCM 213.3). A planned special exposure "shall" only be
authorized when alternatives are unavailable or impractical, the person
in charge specifically makes the request in writing, and joint written
approval is received from the appropriate DOE Headquarters program
office and the Assistant Secretary for Environment, Safety, and Health
(10 CFR 835.204(a) and RCM 213.3). The individual's dose from all
previous planned special exposures and exposures in excess of the
occupational dose limits "shall" be determined prior to a planned special
exposure (10 CFR 835.204(b) and RCM 213.3).
Prior to a planned special exposure, written consent "shall" be obtained
from each individual involved. Each individual "shall" be: (1) informed
of the purpose of the planned operations and procedures to be used; (2)
informed of the estimated doses and associated potential risks and
specific radiological conditions and other hazards which might be
involved in performing the task; and (3) instructed in the measures to
be taken to keep the dose ALARA considering other risks that may be
present (10 CFR 835.204(d) and RCM 213.3).
Planned special exposures "shall" be accounted for separately from routine
exposures received under the occupational dose limits (10 CFR 835.204(a)
and RCM 722.12). The dose from a planned special exposure "shall" be
included in the individual's occupational exposure history (10 CFR
835.204(f) and RCM 722.12) and "shall" be reported to the approving
organizations within 30 days after the exposure (10 CFR 835.204(e) and
RCM 781.4). The dose from a planned special exposure "shall" not be
considered in controlling future occupational dose of the individual (10
CFR 835.204(f) and RCM 213.3 & 722.12).
Section IV, Subsection B - External Dose Evaluation
B. External Dose Evaluation
Radiation protection requirements are expressed in terms of limiting
values of dose equivalent to workers. The limiting values for evaluated
dose equivalent in 10 CFR 835 are specified in terms of TEDE to the
whole body and dose equivalent for other organs and tissues. Total
effective dose equivalents and organ/tissue dose equivalents are
calculated for each calendar year (1) to demonstrate conformance with
limiting values for occupational exposure, (2) to evaluate the
effectiveness of the facility's radiation monitoring program, (3) to
provide a summary report of doses to the worker, and (4) to provide data
for the DOE annual exposure report. The need may also arise to evaluate
doses over shorter time periods such as a month or a quarter year to
meet administrative requirements and controls and to project an
estimated annual dose equivalent to avoid overexposures. Exposures
greater than a predetermined threshold should trigger an investigation
and possible further restrictions on an individual.
The methods for evaluating the various doses from external exposures
should be specified in the External Dosimetry Technical Basis Document.
The methods should be based on recommendations given in ICRP Publication
26, "Recommendations of the International Commission on Radiation
Protection" (ICRP, 1977), NCRP Report No. 91, "Recommendations on Limits
for Exposure to Ionizing Radiation" (NCRP, 1987), and other reports of
the ICRP and NCRP which embody improvements and updates of the science
of external dosimetry. Other methods may be used provided they are
documented and justified in the procedures and/or External Dosimetry
Technical Basis Document. The dose calculation methodology "shall" use
the quality factors and tissue or organ weighting factors in 10 CFR
835.2(b)(10 CFR 835.203(b) and (c) and RCM Table 2-1, Note 1 & Appendix
2B, Note 3).
1. Required Dose Calculations
When an individual is provided with the appropriate personnel
dosimeters, the external dosimetry staff "shall" (10 CFR 835.702(c)(3) &
(5)) determine the following:
-- Effective dose equivalent from external sources recieved during the
year;
-- TEDE received during the year;
-- lens of the eye dose equivalent received during the year;
-- shallow dose equivalent to the skin received during the year;
-- shallow dose equivalent to the extremities received during the
year;
-- the sum of the deep dose equivalent for external exposures and the
committed dose equivalent for internal exposures to any organ or
tissue, other than the lens of the eye, received during the year;
and
-- cumulative TEDE since January 1, 1989.
Personnel dosimeters should be calibrated to measure dose equivalent
directly or indirectly through the use of a calibration factor.
Dosimetry services that process dosimeters report personnel doses in
terms of rem and no further calculations need be performed unless
modifying factors are applied. The time and date of receipt of the
results should be recorded with the exposure results. When neutrons are
monitored for separately, the neutron dose equivalent is added to the
non-neutron deep dose equivalent to determine the total whole body deep
dose equivalent. Additional dose assessments shall be performed for each
instance of a lost, damaged or contaminated personnel dosimeter (RCM
512.6). They should also be performed when multiple dosimeters are worn
and when the radiation field is complex and further interpretation of
the dosimeter reading is required.
Occupational external exposures for all personnel included in the
monitoring program should be evaluated regardless of magnitude. Based on
each evaluation, the external component of the TEDE should be calculated
for the calendar year. Where there are multiple evaluations, each
facility may establish minimum evaluation values. Multiple evaluations
result when multiple dosimeters are used for an individual, either
different dosimeters for different types of radiation or different
dosimeters for different work locations.
2. Special Considerations
Personnel dosimeter measurements are the preferred source of data for
evaluating external dose. Workplace monitoring data and other personnel
monitoring data should be used to evaluate external dose if:
-- Personnel dosimeter measurements are not feasible or are not
available; or
-- workplace monitoring programs or other personnel monitoring
programs indicate that a radiation worker is not likely to receive
greater than 100 mrems (1 mSv) effective dose equivalent in a year.
When personnel dosimeter measurements are not available due to lost,
damaged, or contaminated dosimeters or equipment malfunction, a dose
evaluation shall be performed for that period (RCM 512.6). The dose
evaluation should be based on personnel dosimeter results from other
individuals in the same workplace, on previously recorded exposures
(provided no significant changes in exposure rates would be
anticipated), or on area monitoring results of the ambient radiation
levels. These estimated or assigned exposures "shall" be clearly recorded
and maintained as such (10 CFR 835.702(a) & (b) and RCM 722.1, 722.4 &
752). When area monitoring results are used to estimate individual
occupational exposure, the results of surveys, measurements and
calculations used to determine individual occupational exposure from
external sources "shall" be recorded (10 CFR 835.703(b) and RCM 722.4 &
752).
An individual who is provided with multiple dosimeters may have the dose
measured by the highest responding dosimeter assigned as the whole body
dose of record. When multiple dosimeters are employed more than once
during the year, dosimeter results may be summed by location and the
highest total assigned as the whole body dose of record. If weighting
factors are used to calculate effective dose equivalent from external
radiation fields, the weighting factors in 10 CFR 835.2 "shall" be used
(10 CFR 835.203(b) and RCM Table 2-1, Note 1 & Appendix 2B). If
necessary, a compartmentalization methodology may be applied to the
multiple dosimeter results such that the measured dose at the depth of 1
cm (the deep dose equivalent) represents the maximum dose equivalent to
underlying organs and tissues. A calculation of this type provides a
better representation of the risk to the monitored individual and is in
accordance with ICRP Publication 26. Whatever methodology is selected,
all multiple dosimeter results "shall" be recorded (10 CFR 835.702(b) and
RCM 722.1, 722.3 & 722.13). The External Dosimetry Technical Basis
Document should describe the methodology used in determining the dose of
record when multiple dosimeters are used (RCM 512.5).
When supplemental dosimeters are used, the results should be compared to
the results from the primary dosimeter for the same monitoring periods.
If the dose results differ by more than 50% from the primary dosimeter
and the dose from the primary dosimeter is greater than 100 mrems (1
mSv), an investigation should be initiated to explain the difference
(RCM 513.7).
10 CFR 835.205 and Appendix 2C of the RCM place additional requirements
on evaluating and recording doses from non-uniform exposures of the skin
from X-rays, beta radiation, and/or radioactive materials on the skin,
including hot particles. These special requirements are:
(a) When the area of skin exposed is >= 100 cm2, the non-uniform dose
equivalent received during the year "shall" be averaged over the 100
cm2 of skin receiving the maximum dose, then added to any uniform
dose equivalent also received by the skin, and recorded as the
shallow dose equivalent to extremity or skin for the year.
(b) When the area of skin exposed is >= 10 cm2 but < 100 cm2, the
non-uniform dose equivalent to that tissue received during the year
"shall" be determined by:
H = fD
where H is the dose equivalent, averaged over the 1 cm2 of skin
receiving the maximum absorbed dose, D, and f is the fraction of
skin exposed compared to 100 cm2. In no case "shall" an "f" of < 0.1
be used. This value of dose equivalent "shall" be added to any
uniform dose equivalent also received by the skin and recorded as
the shallow dose equivalent to any extremity or the skin for the
year.
(c) When the area of skin exposed is < 10 cm2, the non-uniform dose
equivalent averaged over the 1 cm2 of skin receiving the maximum
adsorbed dose "shall" be evaluated and recorded in the individual's
occupational exposure history as a special entry but it shall not
be included in any other shallow dose equivalent to any extremity
or skin recorded as the dose equivalent for the year.
The RCM also recommends an action level of 100 mrems (1 mSv) for the
evaluation of skin dose from any skin contamination incident (RCM
541.5). Further information regarding hot particles can be found in
NCRP Report No. 106, "Limit for Exposure to 'Hot Particles' on the Skin"
(NCRP, 1989).
Exposure to the skin "shall" be recorded and reported separately, when
monitored (10 CFR 835.702(a) & (b) & 801(a) and RCM 512.4, 722.4 &
781.1). For non-uniform exposures of the skin, the assessment of the
exposed area should be recorded along with the shallow dose equivalent.
If the non-uniform shallow dose equivalent to the skin, caused by
contamination on the skin, does not result in a dose equivalent in
excess of 1 rem (0.01 Sv), then recording the dose is not required (10
CFR 835.702(b))
When a worker has been monitored for extremity exposure at some time
during the calendar year but is not monitored for the entire year, the
shallow dose equivalent from the whole body dosimeter should be used as
the extremity dose of record for periods when extremity dosimeters are
not worn. The extremity dose, when monitored, "shall" be recorded and
reported separately (10 CFR 835.702(a) & (b) & 801(a) and RCM 512.4,
722.4 & 781.1). Non-uniform exposures of the skin of the extremities
from X-rays, beta radiation, and radioactive materials on the skin,
including hot particles, should be credited to the extremity, not the
skin.
The deep dose equivalent to the female worker is considered to be an
adequate estimation of the dose equivalent to the embryo/fetus for
external radiation for the purpose of radiation protection. A dose
evaluation should be made as soon as a female worker declares her
pregnancy in writing. In the absence of information to the contrary,
the exposure rate prior to declaration may be assumed to be constant and
the dose assigned to the embryo/fetus should be the fraction of the dose
corresponding to the time from conception to the time of declaration.
If the worker continues to receive occupational exposure after
declarartion of pregnancy, then the worker's dosimeter should also be
processed following the birth of the child and added to the previous
dosimeter results to determine the total dose equivalent to the
embryo/fetus. The dose equivalent to the embryo/fetus for the entire
pregnancy "shall" be recorded (10 CFR 835.702(c)(6) and RCM 722.8). See
the IG, "Evaluation and Control of Fetal Exposure," G-10 CFR 835/C4, for
additional guidance on dose evaluation methods for the embryo/fetus. If
the dose equivalent to the embryo/fetus is determined to have already
exceeded 0.5 rem (0.005 Sv) by the time a worker provides written
declaration of her pregnancy to her employer, the worker "shall" not be
assigned to tasks where additional occupational exposure is likely
during the remaining gestation period (10 CFR 835.206(c) and RCM 215.3).
3. Combining External Plus Internal Doses
To ensure that the annual limits are not exceeded, the contributions of
internal and external exposures "shall" be summed (10 CFR 835.203(a)).
The effective dose equivalent may be applied to either individual organs
and tissues or the sum over all organs and tissues. The deep dose
equivalent to the whole body may be used as the effective dose
equivalent for external exposures for the purpose of summing the
internal and external components (10 CFR 835.203(a)). For the case of
uniform external irradiation of the whole body, a weighting factor (wT)
equal to 1 may be used in the determination of the effective dose
equivalent (10 CFR 835.203(c) and RCM Appendix 2B, Note 3).
When an internal dose has been confirmed and the dose evaluated, the
individual's annual external effective dose equivalent and the committed
effective dose equivalent from intakes occuring during the year should
be summed. The resulting total effective dose equivalent may then be
compared against appropriate administrative control levels, annual dose
limits, and lifetime control levels. If the internal dose evaluation
results in a committed effective dose equivalent in excess of 25 percent
of the annual limit (1.25 rems (0.0125 Sv)), an estimate of the organ
dose equivalent due to external exposures should be added to the organ
receiving the highest committed dose equivalent from the internal
exposure. This value can then be compared against the 50 rems (0.5 Sv)
organ dose equivalent limit. For this purpose, the deep dose equivalent
may be used as the organ dose equivalent for external exposures.
In the case of a large exposure, actual or suspected, quick initial
estimates should be made based on stay time and dose rate for external
exposure and air sample results for internal exposure. These estimates
should be used to limit further internal and external dose until
dosimeter and bioassay results are available.
Section IV, Subsection C - Guidance for Monitoring in the Workplace
C. Guidance for Monitoring in the Workplace
Routine monitoring of radiation in the work-place is required by 10 CFR
835 and the RCM. The workplace monitoring program "shall" be capable of
measuring ambient radiation dose rates for the purpose of controlling
radiation exposures (10 CFR 835.403(b) and RCM 551.1 & 552.4). In
addition to workplace monitoring using stationary (area) and/or portable
instruments, the RCM also requires an area dosimetry program (RCM 514).
1. Performance Requirements
Area monitoring in the workplace "shall" be routinely performed, as
necessary, to identify and control potential sources of personnel exposure
to radiation and/or radioactive material (10 CFR 835.401(b) and RCM 514.1,
514.3, 551.1 & 552.2). An area monitoring program "shall" be performed to
document radiological conditions in the workplace and to detect the gradual
buildup of radioactive material in the workplace (10 CFR 835.401(a)(2) &
(4) and RCM 514.1 & 551.1).
To ensure that the requirements of 10 CFR 835 and the RCM are met,
workplace monitoring programs should be designed and conducted to
identify conditions under which an individual is likely to be exposed to
ionizing radiation above the minimum monitoring levels required for the
whole body, skin, extremities, and lens of the eye. Portable survey
instruments in conjunction with fixed workplace monitors should be the
primary method for monitoring the workplace. Individual monitoring
results should be used to complement the workplace monitoring program.
Area monitoring dosimeters shall be used to monitor radiation levels in
routinely occupied areas adjacent to areas where radiation sources
and/or radiation-generating devices are located. This requirement does
not apply when the radiation arises solely from low-energy beta sources
(e.g., carbon-14 or tritium)(RCM 514.1). The data from an area
dosimetry program can be used to show that individual monitoring is not
necessary. Each site should evaluate and, if needed, make adjustments,
such as the use of moderating material, to ensure the accuracy of the
response of their area dosimeters.
Area dosimeter results should not routinely be used for assigning
personnel exposure. The results should be used to supplement the
workplace monitoring program and to provide data in the event of an
accident or emergency. Area monitoring dosimeters should be used to
support dosimetry investigations where personnel express concerns about
their work enviroments and exposure to ionizing radiation (RCM 514.2).
They should also be used in Controlled Areas to supplement existing
monitoring programs and to provide data in the event of an emergency
(RCM 514.3).
If airborne radionuclides are present in the workplace, external
exposure "shall" be controlled using the derived air concen-tration (DAC)
values in Appendix C of 10 CFR 835 (10 CFR 835.209(a)). It should be
noted in the external dosimetry technical basis document which
radionuclides could be present and whether the individual dosimeter
responds correctly to the quality of the radiation or whether submersion
exposures should be calculated separately and added to dosimeter
results.
2. Allowance for Physical Characteristics
The specific physical characteristics of the radiation field present
should be taken into account in the design of the monitoring program and
in the evaluation of external dose equivalent. These characteristics
include radiation quality, energy, fluence rate, and direction of
incidence. If certain characteristics are not known, the assumed values
used as the basis for the workplace monitoring program design should be
documented in the External Dosimetry Technical Basis Document. For
instance, if betas are monitored for but the energies are not known, the
energy assumed and rationale used for calibration purposes should be
recorded.
3. Recourse for Technology Shortfall
The technology needed to perform workplace measurements for
characterizing some types of radiation at levels indicative of the
monitoring requirements for the whole body, skin, extremities, and lens
of the eye may not be available. If the performance objectives cannot
be achieved for this reason, the facility should (1) use the best
practicable (state-of-the-art) monitoring methods, and (2) implement
enhanced design, operation, controls, personnel protection equipment,
and procedures to minimize external exposures.
Section IV, Subsection D - Recording External Doses and Related Information
D. Recording External Doses and Related Information
1. Requirements
In general, records "shall" be maintained for all monitored individuals at
DOE facilities to document compliance and, unless otherwise specified,
"shall" be retained until final disposition is authorized by DOE (10 CFR
835.701 and RCM 711, 712.1, 712.3 & 774.1). These records should
include radiation dose records, calibration records, monitoring
procedures, and documentation of radiological worker training or
radiological orientation. The SI units are not authorized for use in
radiation dose records required by 10 CFR 835.4. The following are
external dosimetry recordkeeping requirements:
a. The results of individual external dose monitoring required by 10
CFR 835.402 and doses received during planned special exposures,
accidents, and emergency conditions "shall" be recorded (10 CFR
835.702(a) and RCM 712.1.c, 722.1, 722,12, 723.1 & 731.2).
b. The results of individual external dose measurements that are
performed, but are not required by 10 CFR 835.402, "shall" be
recorded. The dose equivalent from non-uniform exposure of the
skin caused by contamination does not have to be recorded if the
dose is less than 1 rem (0.01 Sv) (10 CFR 835.702(b) and RCM
722.1, 722.3 & 722.13).
c. The records required by 10 CFR 835.702 "shall" be sufficient to
evaluate compli-ance with the occupational exposure limits in 10
CFR 835.202, "shall" be sufficient to provide dose information
necessary to complete the reports required by 10 CFR 835.801, and
"shall" include the following quantities for external dose received
during the year (10 CFR 835.702(c)(1-3) and RCM 712.1, 722.1,
722.4, 723, 732 & 781):
(1) Effective dose equivalent from external sources of radiation
(deep dose equivalent may be used for external exposure)
received during the year;
(2) lens of the eye dose equivalent received during the year;
(3) shallow dose equivalent to the skin received during the year;
and
(4) shallow dose equivalent to the extremities received during the
year.
d. The records required by 10 CFR 835.702 "shall" include the following
quantities for the summation of the external and internal dose (10
CFR 835.702(c)(5) and RCM 722.6, 722.7 & 722.9):
(1) Summation of the effective dose equivalent (or deep dose
equivalent) from external radiation and the committed
effective dose equivalent from intake of radioactive material
incurred during the year;
(2) summation of the deep dose equivalent for external exposure
and the committed dose equivalent to any organ or tissue
assigned an internal dose from any intake of radioactive
material incurred during the year; and
(3) cumulative total effective dose equivalent, which is the sum
of the total effective dose equivalent values since January 1,
1989.
e. The records "shall" include the dose equivalent to the embryo/fetus
of a declared pregnant worker (10 CFR 835.702(c)(6) and RCM 722.8).
The dose equivalent to the embryo/fetus may be calculated as the
summation of the deep dose equivalent to the mother for external
exposure and the committed effective dose equivalent to the
embryo/fetus from intake of radioactive material by the mother
incurred during the entire gestation period. Further information
can be obtained from the IG Evaluation and Control of Fetal
Exposure G-10 CFR 835/C4.
f. Documentation of all occupational exposure received during the
current year "shall" be obtained to demonstrate compliance with the
annual limits. In the absence of formal records of previous
occupational exposure during the year, a written estimate signed by
the individual is acceptable (10 CFR 835.702(d) and RCM 213.1,
213.2 & 721). For individuals without records of exposure for the
current year who were engaged in activities that could have
resulted in occupational radiation exposure, special administrative
controls should be established that are below the facility
administrative control level. In addition, these individuals
should not be considered for planned special exposures.
g. Efforts "shall" be made to obtain records of prior years occupational
exposures (10 CFR 835.702(e) and RCM 721). Three written requests
to previous employers should constitute sufficient effort. To show
compliance with the RCM lifetime control level, an exposure of 1
rem (0.01 Sv) should be assigned for each prior year for which
records were unavailable and the individual was engaged in
activities that could have resulted in occupational radiation
exposure. These notional lifetime dose values are only for the
purpose of managing lifetime exposures and should not be included
in epidemiological studies, medical evaluation programs, or primary
doses of record.
h. Data necessary to allow at a later date the verification,
correction, or recalcula-tion of recorded doses "shall" be generated
and recorded (10 CFR 835.702(g) and RCM 722.3). The data necessary
to support or recalculate doses at a later date should be
maintained pursuant to Section 4 of ANSI N13.6, "Practice for
Occupational Radiation Exposure Records Systems" (ANSI, 1989b).
i. 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.
j. Records shall be kept pursuant to DOE Order 5484.1, "Environmental
Protection, Safety, and Health Protection Information Reporting
Systems" (DOE, 1987b).
k. All required records shall be retained in accordance with DOE Order
1324.2A, "Records Disposition" (DOE, 1988b). When dosimetry records
are stored on easily corruptible media such as magnetic discs or
tape, a back-up system for data and computational results should be
available for recordkeeping.
l. All records required by 10 CFR 835.702(c) "shall" be transferred to
the DOE upon cessation of activities at the site that could cause
exposure to individuals (10 CFR 835.702(h) and RCM 774.1).
The complete records of radiological incid-ents and occurrences
involving personnel exposure shall be retained (RCM 723.1). Records
shall be maintained for all visitors who were monitored, documenting the
completion of visitor radiation safety orientation and monitoring
results (RCM 731). Investigations of employee radiological safety
concerns should also be recorded and maintained.
2. Individual Information
All radiation dose records shall contain sufficient information to
uniquely identify each individual (RCM 722.2). For example, the name
and Social Security Number or Passport Number and country may be
considered as unique identifiers. Records required by 10 CFR 835.702
that are identified with a specific individual "shall" be readily
available to that individual (10 CFR 835.702(f) and RCM 712.4 & 781.1).
The following information should be retrievable along with individual
exposure data:
-- Full name and former names;
-- Social Security Number or other unique identification number such
as a Passport Number and country;
-- date of birth;
-- sex;
-- employment status;
-- occupation code (i.e., job title);
-- principal facility type and building number; and
-- organization code.
When the above personal identifiers change during the year, records
should be kept of the change and the date.
3. Dose Evaluation Information
The results of maintenance and calibration performed on instruments and
devices used for individual monitoring "shall" be documented and
maintained (10 CFR 835.703(d) and RCM 761.1, 761.2 & 761.4). For each
personnel dosimeter (not including supplemental dosimeters) issued, the
following information should be recorded:
-- Period of exposure of the dosimeter;
-- cross reference to the control and calibration dosimeter data;
-- dosimeter (and dosimeter type) identification;
-- the computed dose for each type of radiation monitored for during
the exposure period; and
-- methods and assumptions used for dose evaluation.
4. Dose Evaluation Records
All data used to evaluate individual doses should be recorded, including
dosimeter measurement results, evaluations of non-uniform doses, dose
reconstructions from lost or damaged dosimeters, and evaluations
resulting from anomalous dosimeter results. Recording a dosimeter
measurement result as "less than MDA (Minimum Detectable Amount)" rather
than recording a numerical value is called censoring data, and should be
avoided. All numerical data should be recorded, including zero and
negative results.
All information that is necessary to review or recalculate each
evaluated dose should be recorded including uncensored data, models,
assumptions, parameters, and additional measurement data as appropriate.
The names of the evaluator and reviewer and the outcome of the review
should be recorded. Any reevaluation of external dose performed should
be documented such that a record of the preliminary and final effective
dose equivalent is retained.
Section IV, Subsection E - Reporting Requirements
E. Reporting Requirements
An annual radiation dose report "shall" be provided to each individual
monitored in accordance with 10 CFR 835.402 (10 CFR 835.801(c) and RCM
781). The report "shall" be in writing and include the DOE site or
facility name, the name of the individual, and the individual's social
security number or employee number (10 CFR 835.801(a) and RCM 781). The
report "shall" also include the data specified in 10 CFR 835.702(c) &
801(a) and RCM 781. Other reporting requirements are found in DOE Order
5484.1 and DOE Order 5000.3B, "Occurrence Reporting and Processing of
Operations Information" (DOE, 1993c).
Detailed information concerning any individual's exposure "shall" be made
available to the individual upon request of that individual, consistent
with the provisions of the Privacy Act (5 U.SC. 552a) (10 CFR 835.801(d)
and RCM 712.4).
Upon the request of an individual terminating employment, records of
exposure "shall" be provided to the individual as soon as the data are
available, but not later than 90 days after termination of employment
(10 CFR 835.801(b) and RCM 781.2). Monitoring results, including zero
dose, should be reported to each visitor within 30 days of the end of
the visit, and shall be reported no later than 90 days after the end of
the visit (RCM 732).
When a DOE contractor is required to report to the Department, pursuant
to DOE Order 5000.3B, any exposure of an individual to radiation or
radioactive material, or planned special exposure, the contractor "shall"
also provide that individual with a report on his or her exposure data
included therein. Such a report "shall" be transmitted at a time not
later than the transmittal to the Department (10 CFR 835.801(e) and RCM
781.4).
DOE Order 5484.1 provides reporting requirements for the "Annual
Radiation Dose Summary" for all monitored individuals. As required by
DOE Order 5484.1, annual reports of worker radiation exposures are to be
provided to the designated DOE Records Repository.
As required by DOE Order 5000.3B, reports of external exposure received
by a worker as a result of an off-normal occurrence, unusual occurrence,
planned special exposure, or emergency shall be reported within the
required time frame.
Section IV, Subsection F - Organization, Staffing, Training, and Facilities
F. Organization, Staffing, Training, and Facilities
1. Organization
The external dosimetry program should be part of the radiation
protection organization at each DOE and DOE-contractor facility. The
radiation protection manager should have overall responsibility for the
external dosimetry program. Each external dosimetry program should have
a designated leader with demonstrated expertise in external dose
evaluation.
When elements of the external dosimetry program are performed by a
subcontractor, the radiation protection organization should ensure that
subcontractors meet all requirements in 10 CFR 835, the RCM, applicable
DOE Orders, and the external dosimetry technical basis document.
Additionally, a copy of all relevant subcontractor procedures should be
incorporated in the historical records of the DOE-contractor.
Where one contractor on a multiple-contractor site conducts the external
dosimetry program, or parts thereof, letters of agreement should detail
the responsibilities, authority, and communication requirements of the
respective parties. A copy of this agreement should be in the External
Dosimetry Technical Basis Document and the applicable record file.
2. Staffing
The radiation protection organization management should ensure that the
external dosimetry program is adequately staffed to carry out its
functions. The functions of the external dosimetry program should
generally include monitoring the external exposure of workers to
ionizing radiation, analyzing radiation monitoring and personnel
dosimeter measurement data, performing external dose evaluations for
significant exposures, advising management, preserving dosimetric
records, and reporting external radiation doses to workers.
The analysis of workplace radiation and personnel dosimeter measurement
data and the evaluation of external dose involves complex evaluation and
professional judgment. Personnel with responsibility for external dose
evaluation should have the necessary expertise and skill, based on
appro- priate education and training in conjunction with practical
experience, to perform their assigned duties. It is important that
external dosimetry specialists be capable of recognizing conditions
warranting follow-up actions and dose reevaluation. Personnel should be
familiar with the relevant external dosimetry literature and the
recommendations of national and international scientific organizations
with regard to evaluation of dose from external exposures.
3. Training, Experience, and Continuing Education
Management of the radiation protection organization should establish
minimum qualifications for those staff responsible for evaluating
external doses. The qualifications should include both experience and
education requirements. Minimum education and formal training
requirements should include:
-- Advanced mathematics, such as calculus, differential equations, and
statistical analyses;
-- radiation instrumentation and measurement techniques;
-- computer technology, hardware, and software used for dose
evaluation;
-- anatomy and physiology of the human body and effects of radiation
on biological systems;
-- nuclear radiation physics;
-- principles of radiation dosimetry and national/international
guidance;
-- operational health physics; and
-- technical writing.
Each new external dosimetrist should undergo a period of apprenticeship
commensurate with his/her experience and education. In addition, other
radiation protection staff should be cross-trained in external dose
evaluation to ensure adequate staffing during vacations, absences, and
vacancies.
The program should be supported by trained dosimetry technicians,
counting system and source operators, and clerical staff, all of whom
should receive training commensurate with job requirements.
Management should establish continuing education requirements for all
staff performing external dose evaluations. Retraining and/or
continuing education are essential for maintaining an adequate level of
expertise and familiarity with current concepts and requirements for
external dose evaluation. Retraining should include changes in
procedures, systems or equipment, Federal regulations, and significant
operating events that are relevant to external dosimetry. The same
subjects as listed above under the minimum educational qualifications
should be considered in establishing continuing education requirements.
4. Facilities and Resources
Computational facilities and software tools used by external dosimetry
personnel should be adequate for performing calculations required for
the evaluation of dose from external sources of ionizing radiation.
A library of handbooks, reference materials, scientific publications,
and other resources pertaining to external dosimetry should be readily
available.
Section IV, Subsection G - External Dosimetry Documentation
G. External Dosimetry Documentation
1. External Dosimetry Technical Basis Document
The RCM requires that a technical basis document be developed for the
external dosimetry program (RCM 512.1). The external dosimetry
technical basis document should give (or provide reference to) the
regulatory, scientific, and technical foundation for the external
dosimetry program. The external dosimetry technical basis document
should provide the approach to evaluating external doses from radiation
monitoring and dosimeter data. This document should provide
justification of categories selected for participation in DOELAP
personnel dosimeter performance testing and, as appropriate, should
describe quality assurance procedures for extremity, area, multiple, or
supplementary dosimeters which may be outside of the DOELAP testing
protocol.
The external dosimetry technical basis document should also describe the
physical characteristics of external radiation encountered in the
workplace, methods for calculating external doses, methods for
documenting calculations, dose evaluation quality assurance, and
procedures for recording and reporting external dose results.
The technical basis for evaluating dose from both routine and special
dosimetry and for evaluating data from portable survey instruments and
other radiation monitoring equipment should be included in the external
dosimetry technical basis document. Cali-bration models, parameters,
assumptions, and default values used in dosimetric modeling and
evaluation should be clearly identified. Statistical methods for
evaluating dosimeter data, using appropriate controls, identifying
above-background values, and analyzing trends should be described. The
external dosimetry technical basis document should be reviewed
periodically and updated, as necessary, to assure that the scientific
bases are appropriate for current workplace conditions. The external
dosimetry technical basis document should be a controlled document and
retained as a radiation protection program record.
2. Procedures
All of the functions of the external dosimetry program should be
specified in written procedures. These procedures should be consistent
with 10 CFR 835, the RCM, relevant DOE Orders, and the external
dosimetry technical basis document. In summary, the methods and
requirements for measuring, evaluating, and recording external dose
should be specified. The procedures should specify methods for
consistent collection of workplace and personnel monitoring data, its
evaluation, documentation of results, and records maintenance. The
components of the external dosimetry program and the organization
structure to which it reports should be documented in procedures.
Responsibilities of line management and members of the dose evaluation
group should be described. Elements of the workplace monitoring and
radiation worker monitoring program that are germane to external
dosimetry also should be included. Guidelines for prompt followup of
accidental or emergency exposures to ionizing radiation should be
carefully defined, including the medical management of workers with
excessive exposures.
The procedures should be reviewed at least once every two years and
updated as necessary. The requirements for maintenance of procedures
should be specified, including responsibilities for authorship, review,
approval, and distribution.
Section IV, Subsection H - Medical Responce
H. Medical Response
Facilities with potential for exposures approaching dose limits should
be prepared to follow an action plan for medical response to any
potential or unplanned exposure in excess of the limits. The plan
should be developed as a cooperative effort between medical and
radiation protection organizations and should include mobilizing key
response functions (external dosimetry, activation counting, medical
assistance, etc.), training, and action levels for response. The
elements of this plan should include:
-- Action levels for medical response;
-- responsibilities of the affected worker, radiation protection
staff, external dose evaluation staff, health physicists, medical
staff, and line management;
-- guides for immediate medical care, decontamination, monitoring, and
long-term evaluation; and
-- provision for periodically reviewing, updating, and rehearsing the
action plan.
Planning for such emergency actions should include the provision of
facilities and supplies for the treatment of workers, if necessary,
after identification of a medically significant exposure. Action levels
should be established in the external dosimetry technical basis document
based on decisions reached among radiation protection, medical, and
management staff.
Section IV, Subsection I - Quality Assurance
I. Quality Assurance
1. General Requirement
From the initial step of issuing dosimeters through dosimeter readout
and dose evaluation to recording of the results, every step in an
external dosimetry program is important in protecting workers and in
demonstrating compliance with 10 CFR 835, the RCM, and DOE Orders. All
steps in the activities that control or evaluate worker external doses
should be covered by written procedures that provide appropriate quality
control and quality assurance. Quality assurance practices, such as
supervisors ensuring that radiation surveys are performed with
appropriate frequency, will provide corrective action when necessary.
Quality control will provide the needed documents and records for
demonstrating compliance.
Computer software used to perform external dose evaluations should also
be controlled according to software quality assurance procedures.
Procedures for software quality assurance should address:
-- Software documentation per ANSI/ANS 10.3, "Guidelines for the
Documentation of Digital Computer Programs" (ANSI, 1986);
-- validation and verification of models, data, assumptions, and
algorithms per ANSI/ANS 10.4, "Verification and Validation of
Scientific and Engineering Computer Programs for the Nuclear
Industry" (ANSI, 1987);
-- software security;
-- configuration management;
-- periodic testing to ensure proper function; and
-- actions to be taken in the event that software errors are detected.
Hand calculations should be independently verified by a second qualified
individual and the review documented.
2. Independent Review
The external dosimetry program should receive periodic assessment by the
site radiation protection organization to review technical basis
documentation, dose assessment procedures, instrumentation and
analytical methods, personnel qualifications, quality assurance program
elements, and other elements of the program, as necessary to assure that
the program maintains the capability to stay abreast of scientific
developments in external dosimetry and provides a quality radiation
protection service to workers. Internal audits of all functional
elements of the radiation protection program should be conducted as
often as necessary, however, they "shall" be conducted no less frequently
than every three years and "shall" include program content and
implementation (10 CFR 835.102 and RCM 134.1). External peer-review by
qualified individuals, on a periodic basis, is also recommended.
Section V - References
V. REFERENCES
(AEC, 1954) Atomic Energy Act of 1954, as amended, Public Law 83-703 (68
Stat. 919), Title 42 U.S.C. sec. 2011.
(ANSI, 1986) American National Standards Institute. 1986. "Guidelines
for the Documentation of Digital Computer Programs." ANSI/ANS 10.3-1986.
LaGrange Park, Illinois.
(ANSI, 1987) American National Standards Institute. 1987.
"Verification and Validation of Scientific and Engineering Computer
Programs for the Nuclear Industry." ANSI/ANS 10.4-1986. LaGrange Park,
Illinois.
(ANSI, 1989a) American National Standards Institute. 1989.
"Performance Specification for Direct Reading and Indirect Reading Pocket
Dosimeters for X- and Gamma Radiation." ANSI N13.5-1972(R1989). New
York, New York.
(ANSI, 1989b) American National Standards Institute. 1989. "Practice
for Occupational Radiation Exposure Records Systems." ANSI N13.6-1966
(R1989). New York, New York.
(ANSI, 1992) American National Standards Institute. 1992. "Performance
Requirements for Pocket-Sized Alarm Dosimeters and Alarm Rate Meters."
ANSI N13.27-1981 (R1992), New York, New York.
(BRH, 1970) Bureau of Radiological Health. 1970. "Radiological Health
Handbook." U.S. Government Printing Office. Washington, D.C.
(DOE, 1987a) U.S. Department of Energy. 1987. "Safety of Nuclear
Facilities." DOE Order 5480.5. Washington, D.C.
(DOE, 1987b) U.S. Department of Energy. 1987. "Environmental
Protection, Safety, and Health Protection Information Reporting System."
DOE Order 5484.1. Washington, D.C.
(DOE, 1988a) U.S. Department of Energy, 1988. "Department of Energy
Laboratory Accreditation Program for Personnel Dosimetry." DOE Order
5480.15. Washington, D.C.
(DOE, 1988b) U.S. Department of Energy. 1988. "Records Disposition." DOE
Order 1324.2A. Washington, D.C.
(DOE, 1992) U.S. Department of Energy. 1988. "Radiation Protection for
Occupational Workers." DOE Order 5480.11, Change 1: July 17, 1992.
Washington, D.C.
(DOE, 1993a) U.S. Department of Energy. 1993. "Occupational Radiation
Protection." 10 CFR 835, 58 FR 65458. Federal Register Vol. 58, No. 236:
December 14, 1993. Washington, D.C.
(DOE, 1993b) U.S. Department of Energy. 1993. "Procedural Rules for DOE
Nuclear Activities." 10 CFR 820, 58 FR 43680. Federal Register Vol. 58,
No. 157: August 17, 1993. Washington, D.C.
(DOE, 1993c) U.S. Department of Energy. 1993. "Occurrence Reporting and
Processing of Operations Information." DOE Order 5000.3B. Washington,
D.C.
(DOE, 1994a) U.S. Department of Energy. 1994. "Radiological Control
Manual." DOE/EH-0256T. Washington, D.C.
(DOE, 1994b) U.S. Department of Energy. 1994. "Implementation Guide for
10 CFR 835 - Evaluation and Control of Fetal Exposure." G-10 CFR 835/C4 -
Rev. 1. Washington, D.C.
(EPA, 1987) Environmental Protection Agency. 1987. "Radiation
Protection Guidance to Federal Agencies for Occupational
Exposure--Recommendations Approved by the President." Federal Register
52(17):2822-2834, January 27, 1987.
(ICRP, 1977) International Commission on Radiological Protection.
1977. "Recommendation of the International Commission on Radiological
Protection." ICRP Publication 26. Pergamon Press. New York, New
York.
(ICRU, 1988) International Commisson on Radiation Units and
Measurements. 1988. "Determination of Dose Equivalents from External
Radiation Sources - Part 2." ICRU Report No. 43. Bethesda, Maryland.
(NCRP, 1987) National Council on Radiation Protection and Measurements.
1987. "Recommendations on Limits for Exposure to Ionizing Radiation." NCRP
Report No. 91. Bethesda, Maryland.
(NCRP, 1989) National Council on Radiation Protection and Measurements.
1989. "Limit for Exposure to 'Hot Particles' on the Skin." NCRP Report
No. 106. Bethesda, Maryland.
Section VI - Supporting Documents
VI. SUPPORTING DOCUMENTS
Brackenbush, L. W., K. R. Heid, W. N. Herrington, J. L. Kenoyer, L. F.
Munson, L. H. Munson, J. M. Selby, K. L. Soldat, G. A. Stoetzel, and R.
J. Traub. 1988. "Health Physics Manual of Good Practices for Plutonium
Facilities." PNL-6534. Pacific Northwest Laboratory. Richland,
Washington.
International Commission on Radiological Protection. 1990. 1990
"Recommendations of the International Commission on Radiological
Protection." ICRP Publication 60. Pergamon Press. New York, New York.
Rich, B. L., S. L. Hinnefeld, C. R. Lagerquist, W. G. Mansfield, L. H.
Munson, and E. R. Wagner. 1988. "Health Physics Manual of Good
Practices for Uranium Facilities." EGG-2530. EG&G Idaho, Inc., Idaho
Falls, Idaho.
Thind, K. S. 1987. "Extremity Dose: Its Definition, Standards and
Regulatory Limits, Radiobiological Significance, Measurement and
Practical Considerations." Health Physics 52(6):695-705.
Section VII - Appendix
APPENDIX
10 CFR 835, Implementation Guide, and DOE Radiological Control
Manual Cross-Reference
10 CFR 835 Implementation Guide Radiological Control Manual
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835.2 II & IV.A.3 Glossary
835.4 IV -
835.102 IV 127 & 134
835.202 III 213
835.203 III, IV.B, IV.B.2 & 3 Chapter 2
835.204 IV.A.6 213.3, 722.12 & 781.4
835.205 IV.B.2 Appendix 2C
835.206 III & IV.B.2 215
835.207 III Table 2-1
835.208 III Table 2-1
835.209 III and IV.C.1 223
835.401 III, IV.A.1 & IV.C.1 Chapter 5
835.402 III, IV.A & IV.A.3 Chapter 5, Parts 1 & 2
835.403 IV.C 514 & 553
835.701 IV.D.1 711
835.702 III, IV, IV.A, IV.A.2, 712, 722, 723.1, 731 & 781
IV.A.3, IV.D.1 & IV.E
835.703 IV, IV.B.2 & IV.A.3 751, 752 & 761
835.801 IV.A.3 & IV.E 712 & 781
835.1003 III 511.1 & 551.1
835.1304 IV.A.3 & IV.A.5 515
835.1204 IV.A.5 515
Change Request Form
UNITED STATES DEPARTMENT OF ENERGY
Office of Health Physics and Industrial Hygiene (EH-41, 270 CC/GTN)
Washington, DC 20585
REQUEST FOR CHANGES TO IMPLEMENTATION GUIDE ON EXTERNAL
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Contact: Steve G. Zobel, (301) 903-2305