ASTM E1034-95e1
(Specification)Standard Specification for Nuclear Facility Transient Worker Records
Standard Specification for Nuclear Facility Transient Worker Records
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.
1.2 This specification applies to records to be used for in-processing only.
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).
1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers. Note 2—This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).
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e1
Designation: E 1034 – 95
Standard Specification for
Nuclear Facility Transient Worker Records
This standard is issued under the fixed designation E 1034; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
e NOTE—Editorial changes were made throughout in February 1996.
INTRODUCTION
There is a high degree of concern in the nuclear industry regarding the ability of present records
keeping practices to adequately monitor the cumulative radiation doses of individual transient
workers. This concern arises from the fact that the transient worker moves rapidly among the nuclear
facilities, in some cases working at as many as four or more facilities within one calendar quarter. The
accurate monitoring of a transient worker’s cumulative radiation dose depends, in part, on the
individual worker’s ability (and willingness) to provide a correct record of his occupational radiation
exposure. At nuclear facilities licensed by the U.S. Nuclear Regulatory Commission (NRC), these data
presently are supplied by the worker on forms NRC-4 and NRC-5. Similar procedures are followed
at other nuclear facilities (see Note 1). Accurate occupational radiation exposure data are required to
ensure that the radiation doses that an individual transient worker will receive are within regulatory
limits.
Another problem confronting the owners of nuclear facilities is how to in-process large numbers of
temporary workers efficiently. These workers may be required for such activities as the decontami-
nation and decommissioning of a nuclear facility, the annual refueling of a nuclear power plant, or a
major special modification to an operating nuclear facility. In-processing involves determining a
worker’s occupational radiation exposure history, security clearance, health status, ability to wear and
use respiratory protective equipment, and training and qualification for work in controlled areas.
In-processing is the responsibility of the licensee, and depends on the cooperation of the worker and
the worker’s present and past employers and other past contracting licensees.
In-processing is complicated by the fact that different facilities keep the required information on
different forms in varying degrees of detail. In-processing one worker often can take several days and
result in a loss of productive time as well as increased staffing costs for the facility operator.
One possible solution to these problems is a cooperative effort within the nuclear industry to
develop a common or central data base that can be accessed to obtain pertinent historical data on a
worker. A central record keeping system (CRS) is envisioned for this purpose. Such a system could
help reduce in-processing time for temporary workers.
However, some degree of standardization is necessary before a centralized record keeping system
is possible. This specification standardizes the necessary content of transient worker records.
1. Scope tion qualifications, or welding certifications).
1.4 This specification does not reduce any regulatory re-
1.1 This specification covers the required content and pro-
quirement for records retention at a licensed nuclear facility.
vides retention requirements for records needed for in-
processing of nuclear facility transient workers.
NOTE 1—Nuclear facilities operated by the U.S. Department of Energy
1.2 This specification applies to records to be used for
(DOE) are not licensed by the U.S. Nuclear Regulatory Commission
(NRC), nor are other nuclear facilities that may come under the control of
in-processing only.
the U.S. Department of Defense (DOD) or individual agreement states.
1.3 This specification is not intended to cover specific skills
The references in this specification to licensee, the U.S. NRC Regulatory
records (such as equipment operating licenses, ASME inspec-
Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply
appropriate alternative nomenclature with respect to DOE, DOD, or
This specification is under the jurisdiction of ASTM Committee E-10 on
agreement state nuclear facilities. This distinction does not alter the
Nuclear Technology and Applications and is the direct responsibility of Subcom-
required content of records needed for in-processing of nuclear facility
mittee E10.03 on Radiological Protection for Decontamination and Decommission-
transient workers.
ing of Nuclear Facilities and Components.
NOTE 2—This specification does not define the form of the required
Current edition approved Oct. 10, 1995. Published December 1995.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
E 1034
worker records (such as a passport or central computerized record keeping
ensees. It is not the same as the controlled area definition with
system).
which NRC and Agreement State Licensees are familiar.
3.1.5 deep dose equivalent (DDE), n—dose equivalent de-
2. Referenced Documents
livered to tissue at a depth of 1.0 cm or more from the surface.
2.1 ASTM Standards:
3.1.6 dose equivalent (H), n—the product of D, Q, and N,at
E 1168 Guide for Radiological Protection Training for
the point of interest in tissue, where D is the absorbed dose, Q
Nuclear Facility Workers
is the quality factor, and N is the product of any other
2.2 ANSI Standards:
modifying factors.
ANSI/ANS-3.3-1982 Security for Nuclear Power Plants
3.1.6.1 Discussion—The SI unit of dose equivalent is the
ANSI N13.6 American National Standard Practice for Oc-
sievert (equal to 1 J/kg). The traditional unit of dose equivalent
cupational Radiation Exposure Records Systems
is the rem. One Sv 5 100 rem.
2.3 Nuclear Regulatory Commission Documents:
3.1.7 employer, n—a person or concern that employs per-
Regulatory Guide 8.7, Instructions for Recording and Re-
sons for wages or salary. Note that a worker may have more
porting Occupational Radiation Exposure Data
than one employer at a given time.
Regulatory Guide 8.15, Acceptable Programs for Respira-
3.1.8 estimated dose, n—dose data supplied by the licensee
tory Protection
to the worker prior to the determination of the official record
NUREG-0041, Manual of Respiratory Protection Against
dose (see section 10CFR Part 19 or equivalent).
Airborne Radioactive Materials
3.1.8.1 Discussion—Estimated doses are provided at the
2.4 CFR Documents:
worker’s request and generally when the worker is terminating
Notices, Instructions, and Reports to Workers; Inspections,
a work assignment involving radiation exposure at a licensee’s
10CFR, Part 19
facility.
Standards for Protection Against Radiation, 10CFR, Part
3.1.9 external dose equivalent, n—dose equivalent due to
radiation sources located outside the body.
2.5 American Nuclear Insurers Documents:
3.1.10 extremity, n—hands and arms below the elbow or
ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-
feet and legs below the knee (see 3.1.23).
ity Insurance Records Retention
3.1.11 extremity dose, n—the external (shallow/deep) dose
to the extremities.
3. Terminology
3.1.12 eye dose equivalent, n—dose equivalent to the lens
3.1 Descriptions of Terms Specific to This Standard:
of the eye from external radiation sources is taken as the dose
3.1.1 absorbed dose(D), n—for purposes of records main-
equivalent at a tissue depth of 0.3 cm (300 mg/cm ).
tained in accordance with this specification, absorbed dose is
3.1.13 in-processing, n—the determination, prior to starting
the energy absorbed per unit mass at a specific place in a
work, of a worker’s previous occupational radiation exposure
material.
history, security clearance, health status, ability to wear and use
3.1.1.1 Discussion—The SI unit of absorbed dose is the
respiratory and other personal protective equipment, and train-
gray (Gy), equal to 1 J/kg (10,000 ergs/g). The traditional unit
ing and qualification for work in controlled areas.
of absorbed dose is the rad. One Gy 5 100 rad. As used in this
3.1.14 nuclear facility, n—a facility whose operations in-
specification, “absorbed dose” stands for the absorbed dose in
volve (or involved) radioactive materials in such form and
soft tissue.
quantity that a nuclear hazard potentially exists (or existed) to
3.1.2 committed dose equivalent (CDE), n—dose equivalent
the employees and the general public. Included are facilities
to organs or tissues of reference that will be received from an
that are (or were) used to produce, process, or store radioactive
intake of radioactive material by an individual during the
materials (see Note 1). Some examples are: nuclear reactor
50-year period following the intake.
(power or research), fuel fabrication plant, fuel reprocessing
3.1.3 committed effective dose equivalent (CEDE), n—the
plant, uranium or thorium mill, UF production plant, radio-
sum of the committed dose equivalents to various tissues in the
chemical laboratory, and radioactive waste disposal site.
body, each multiplied by its weighting factor. It does not
3.1.15 occupational radiation exposure, n—radiation expo-
include contributions from external dose.
sure resulting from, and received in, the course of an individu-
3.1.4 controlled area, n—an area of a nuclear facility
al’s employment.
encompassed by physical barriers to which access is con-
3.1.16 offıcial record dose, n—dose data supplied by the
trolled.
licensee to the worker and the NRC in accordance with
3.1.4.1 Discussion—This definition is equivalent to the
10CFR20.2206 (or equivalent).
restricted area definition for NRC and Agreement State Lic-
3.1.17 radiation, n—in the context of this specification,
“radiation” refers to ionizing radiation. Ionizing radiation is
any electromagnetic or particulate radiation capable of produc-
Annual Book of ASTM Standards, Vol 12.02.
ing ions, directly or indirectly, by interaction with matter.
Available from American National Standards Institute, 11 W. 42nd St., 13th
Floor, New York, NY 10036.
3.1.18 radiation exposure, n—in the context of this speci-
Available from the Superintendent of Documents, U.S. Government Printing
fication, “exposure” refers very broadly to the act or state of
Office, Washington, DC 20402.
5 being irradiated by ionizing radiation.
Available from American Nuclear Insurers, 29 Sou
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