ASTM E1034-95(2001)
(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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Standards Content (Sample)
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Designation: E 1034 – 95 (Reapproved 2001)
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.
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.AtnuclearfacilitieslicensedbytheU.S.NuclearRegulatoryCommission(NRC),thesedata
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 1.2 This specification applies to records to be used for
in-processing only.
1.1 This specification covers the required content and pro-
1.3 This specification is not intended to cover specific skills
vides retention requirements for records needed for in-
records (such as equipment operating licenses, ASME inspec-
processing of nuclear facility transient workers.
tion qualifications, or welding certifications).
1.4 This specification does not reduce any regulatory re-
This specification is under the jurisdiction of ASTM Committee E10 on quirement for records retention at a licensed nuclear facility.
Nuclear Technology and Applications and is the direct responsibility of Subcom-
NOTE 1—Nuclear facilities operated by the U.S. Department of Energy
mittee E10.03 on Radiological Protection for Decontamination and Decommission-
(DOE) are not licensed by the U.S. Nuclear Regulatory Commission
ing of Nuclear Facilities and Components.
Current edition approved Oct. 10, 1995. Published December 1995. (NRC), nor are other nuclear facilities that may come under the control of
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E 1034
the U.S. Department of Defense (DOD) or individual agreement states.
body, each multiplied by its weighting factor. It does not
The references in this specification to licensee, the U.S. NRC Regulatory
include contributions from external dose.
Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply
3.1.4 controlled area, n—an area of a nuclear facility
appropriate alternative nomenclature with respect to DOE, DOD, or
encompassed by physical barriers to which access is con-
agreement state nuclear facilities. This distinction does not alter the
trolled.
required content of records needed for in-processing of nuclear facility
transient workers.
3.1.4.1 Discussion—This definition is equivalent to the
NOTE 2—This specification does not define the form of the required
restricted area definition for NRC and Agreement State Lic-
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 = 100 rem.
2.3 Nuclear Regulatory Commission Documents:
Regulatory Guide 8.7, Instructions for Recording and Re-
3.1.7 employer, n—a person or concern that employs per-
porting Occupational Radiation Exposure Data sons for wages or salary. Note that a worker may have more
Regulatory Guide 8.15, Acceptable Programs for Respira-
than one employer at a given time.
tory Protection
3.1.8 estimated dose, n—dose data supplied by the licensee
NUREG-0041, Manual of Respiratory Protection Against
to the worker prior to the determination of the official record
Airborne Radioactive Materials
dose (see section 10CFR Part 19 or equivalent).
2.4 CFR Documents:
3.1.8.1 Discussion—Estimated doses are provided at the
Notices, Instructions, and Reports to Workers; Inspections,
worker’s request and generally when the worker is terminating
10CFR, Part 19
a work assignment involving radiation exposure at a licensee’s
Standards for Protection Against Radiation, 10CFR, Part
facility.
3.1.9 external dose equivalent, n—dose equivalent due to
2.5 American Nuclear Insurers Documents:
radiation sources located outside the body.
ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-
3.1.10 extremity, n—hands and arms below the elbow or
ity Insurance Records Retention
feet and legs below the knee (see 3.1.23).
3.1.11 extremity dose, n—the external (shallow/deep) dose
3. Terminology
to the extremities.
3.1 Descriptions of Terms Specific to This Standard:
3.1.12 eye dose equivalent, n—dose equivalent to the lens
3.1.1 absorbed dose(D), n—for purposes of records main-
of the eye from external radiation sources is taken as the dose
tained in accordance with this specification, absorbed dose is
equivalent at a tissue depth of 0.3 cm (300 mg/cm ).
the energy absorbed per unit mass at a specific place in a
3.1.13 in-processing, n—the determination, prior to starting
material.
work, of a worker’s previous occupational radiation exposure
3.1.1.1 Discussion—The SI unit of absorbed dose is the
history,securityclearance,healthstatus,abilitytowearanduse
gray (Gy), equal to 1 J/kg (10,000 ergs/g). The traditional unit
respiratory and other personal protective equipment, and train-
of absorbed dose is the rad. One Gy = 100 rad.As used in this
ing and qualification for work in controlled areas.
specification, “absorbed dose” stands for the absorbed dose in
3.1.14 nuclear facility, n—a facility whose operations in-
soft tissue.
volve (or involved) radioactive materials in such form and
3.1.2 committed dose equivalent (CDE), n—doseequivalent
quantity that a nuclear hazard potentially exists (or existed) to
to organs or tissues of reference that will be received from an
the employees and the general public. Included are facilities
intake of radioactive material by an individual during the
that are (or were) used to produce, process, or store radioactive
50-year period following the intake.
materials (see Note 1). Some examples are: nuclear reactor
3.1.3 committed effective dose equivalent (CEDE), n—the
(power or research), fuel fabrication plant, fuel reprocessing
sum of the committed dose equivalents to various tissues in the
plant, uranium or thorium mill, UF production plant, radio-
chemical laboratory, and radioactive waste disposal site.
3.1.15 occupational radiation exposure, n—radiation expo-
Annual Book of ASTM Standards, Vol 12.02.
sure resulting from, and received in, the course of an individu-
Available from American National Standards Institute, 11 W. 42nd St., 13th
Floor, New York, NY 10036. al’s employment.
Available from the Superintendent of Documents, U.S. Government Printing
3.1.16 offıcial record dose, n—dose data supplied by the
Office, Washington, DC 20402.
licensee to the worker and the NRC in accordance with
Available from American Nuclear Insurers, 29 South Main (Suite 300S), West
Hartford, CT 06107-2445. 10CFR20.2206 (or equivalent).
E 1034
3.1.17 radiation, n—in the context of this specification, 5.1.4 Permanent address.
“radiation” refers to ionizing radiation. Ionizing radiation is 5.1.5 Verification that the data contained in the worker’s
any electromagnetic or particulate radiation capable of produc- record have bee
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