1、Designation: E 1034 95 (Reapproved 2001)Standard Specification forNuclear Facility Transient Worker Records1This standard is issued under the fixed designation E 1034; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of las
2、t revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.INTRODUCTIONThere is a high degree of concern in the nuclear industry regarding the ability of present recordskeeping practices to a
3、dequately monitor the cumulative radiation doses of individual transientworkers. This concern arises from the fact that the transient worker moves rapidly among the nuclearfacilities, in some cases working at as many as four or more facilities within one calendar quarter. Theaccurate monitoring of a
4、 transient workers cumulative radiation dose depends, in part, on theindividual workers ability (and willingness) to provide a correct record of his occupational radiationexposure. At nuclear facilities licensed by the U.S. Nuclear Regulatory Commission (NRC), these datapresently are supplied by the
5、 worker on forms NRC-4 and NRC-5. Similar procedures are followedat other nuclear facilities (see Note 1). Accurate occupational radiation exposure data are required toensure that the radiation doses that an individual transient worker will receive are within regulatorylimits.Another problem confron
6、ting the owners of nuclear facilities is how to in-process large numbers oftemporary 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 amajor special modification
7、 to an operating nuclear facility. In-processing involves determining aworkers occupational radiation exposure history, security clearance, health status, ability to wear anduse respiratory protective equipment, and training and qualification for work in controlled areas.In-processing is the respons
8、ibility of the licensee, and depends on the cooperation of the worker andthe workers present and past employers and other past contracting licensees.In-processing is complicated by the fact that different facilities keep the required information ondifferent forms in varying degrees of detail. In-pro
9、cessing one worker often can take several days andresult 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 todevelop a common or central data base that can be accessed
10、 to obtain pertinent historical data on aworker. A central record keeping system (CRS) is envisioned for this purpose. Such a system couldhelp reduce in-processing time for temporary workers.However, some degree of standardization is necessary before a centralized record keeping systemis possible. T
11、his specification standardizes the necessary content of transient worker records.1. Scope1.1 This specification covers the required content and pro-vides retention requirements for records needed for in-processing of nuclear facility transient workers.1.2 This specification applies to records to be
12、used forin-processing only.1.3 This specification is not intended to cover specific skillsrecords (such as equipment operating licenses, ASME inspec-tion qualifications, or welding certifications).1.4 This specification does not reduce any regulatory re-quirement for records retention at a licensed
13、nuclear facility.NOTE 1Nuclear 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 ofthe U.S. Department of Defense (DOD) or individual agreement states.The referen
14、ces in this specification to licensee, the U.S. NRC RegulatoryGuides, and Title 10 of the U.S. Code of Federal Regulations are to implyappropriate alternative nomenclature with respect to DOE, DOD, oragreement state nuclear facilities. This distinction does not alter therequired content of records n
15、eeded for in-processing of nuclear facilitytransient workers.NOTE 2This specification does not define the form of the required1This specification is under the jurisdiction of ASTM Committee E10 onNuclear Technology and Applications and is the direct responsibility of Subcom-mittee E10.03 on Radiolog
16、ical Protection for Decontamination and Decommission-ing of Nuclear Facilities and Components.Current edition approved Oct. 10, 1995. Published December 1995.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.worker records (such as a p
17、assport or central computerized record keepingsystem).2. Referenced Documents2.1 ASTM Standards:E 1168 Guide for Radiological Protection Training forNuclear Facility Workers22.2 ANSI Standards:ANSI/ANS-3.3-1982 Security for Nuclear Power Plants3ANSI N13.6 American National Standard Practice for Oc-c
18、upational Radiation Exposure Records Systems32.3 Nuclear Regulatory Commission Documents:Regulatory Guide 8.7, Instructions for Recording and Re-porting Occupational Radiation Exposure Data4Regulatory Guide 8.15, Acceptable Programs for Respira-tory Protection4NUREG-0041, Manual of Respiratory Prote
19、ction AgainstAirborne Radioactive Materials42.4 CFR Documents:Notices, Instructions, and Reports to Workers; Inspections,10CFR, Part 194Standards for Protection Against Radiation, 10CFR, Part2042.5 American Nuclear Insurers Documents:ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-ity Insurance
20、 Records Retention53. Terminology3.1 Descriptions of Terms Specific to This Standard:3.1.1 absorbed dose(D), nfor purposes of records main-tained in accordance with this specification, absorbed dose isthe energy absorbed per unit mass at a specific place in amaterial.3.1.1.1 DiscussionThe SI unit of
21、 absorbed dose is thegray (Gy), equal to 1 J/kg (10,000 ergs/g). The traditional unitof absorbed dose is the rad. One Gy = 100 rad. As used in thisspecification, “absorbed dose” stands for the absorbed dose insoft tissue.3.1.2 committed dose equivalent (CDE), ndose equivalentto organs or tissues of
22、reference that will be received from anintake of radioactive material by an individual during the50-year period following the intake.3.1.3 committed effective dose equivalent (CEDE), nthesum of the committed dose equivalents to various tissues in thebody, each multiplied by its weighting factor. It
23、does notinclude contributions from external dose.3.1.4 controlled area, nan area of a nuclear facilityencompassed by physical barriers to which access is con-trolled.3.1.4.1 DiscussionThis definition is equivalent to therestricted area definition for NRC and Agreement State Lic-ensees. It is not the
24、 same as the controlled area definition withwhich NRC and Agreement State Licensees are familiar.3.1.5 deep dose equivalent (DDE), ndose equivalent de-livered to tissue at a depth of 1.0 cm or more from the surface.3.1.6 dose equivalent (H), nthe product of D, Q, and N,atthe point of interest in tis
25、sue, where D is the absorbed dose, Qis the quality factor, and N is the product of any othermodifying factors.3.1.6.1 DiscussionThe SI unit of dose equivalent is thesievert (equal to 1 J/kg). The traditional unit of dose equivalentis the rem. One Sv = 100 rem.3.1.7 employer, na person or concern tha
26、t employs per-sons for wages or salary. Note that a worker may have morethan one employer at a given time.3.1.8 estimated dose, ndose data supplied by the licenseeto the worker prior to the determination of the official recorddose (see section 10CFR Part 19 or equivalent).3.1.8.1 DiscussionEstimated
27、 doses are provided at theworkers request and generally when the worker is terminatinga work assignment involving radiation exposure at a licenseesfacility.3.1.9 external dose equivalent, ndose equivalent due toradiation sources located outside the body.3.1.10 extremity, nhands and arms below the el
28、bow orfeet and legs below the knee (see 3.1.23).3.1.11 extremity dose, nthe external (shallow/deep) doseto the extremities.3.1.12 eye dose equivalent, ndose equivalent to the lensof the eye from external radiation sources is taken as the doseequivalent at a tissue depth of 0.3 cm (300 mg/cm2).3.1.13
29、 in-processing, nthe determination, prior to startingwork, of a workers previous occupational radiation exposurehistory, security clearance, health status, ability to wear and userespiratory and other personal protective equipment, and train-ing and qualification for work in controlled areas.3.1.14
30、nuclear facility, na facility whose operations in-volve (or involved) radioactive materials in such form andquantity that a nuclear hazard potentially exists (or existed) tothe employees and the general public. Included are facilitiesthat are (or were) used to produce, process, or store radioactivem
31、aterials (see Note 1). Some examples are: nuclear reactor(power or research), fuel fabrication plant, fuel reprocessingplant, uranium or thorium mill, UF6production plant, radio-chemical laboratory, and radioactive waste disposal site.3.1.15 occupational radiation exposure, nradiation expo-sure resu
32、lting from, and received in, the course of an individu-als employment.3.1.16 offcial record dose, ndose data supplied by thelicensee to the worker and the NRC in accordance with10CFR20.2206 (or equivalent).3.1.17 radiation, nin the context of this specification,“radiation” refers to ionizing radiati
33、on. Ionizing radiation isany electromagnetic or particulate radiation capable of produc-ing ions, directly or indirectly, by interaction with matter.3.1.18 radiation exposure, nin the context of this speci-fication, “exposure” refers very broadly to the act or state ofbeing irradiated by ionizing ra
34、diation.3.1.19 shallow dose equivalent (SDE), ndose equivalent2Annual Book of ASTM Standards, Vol 12.02.3Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.4Available from the Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC
35、 20402.5Available from American Nuclear Insurers, 29 South Main (Suite 300S), WestHartford, CT 06107-2445.E 10342delivered to the skin or an extremity at a tissue depth of 0.007cm (7 mg/cm2) averaged over an area of 1 square centimeter.3.1.19.1 DiscussionDOE reporting requirements in 10CFR 835.205 i
36、nclude provisions for assessing nonuniformexposures of the skin from X-rays, beta radiation, or radioac-tive materials on the skin, or a combination thereof. Thisassessment addresses affected skin areas of: $ 100 cm2, 100cm2but $ 10 cm2,and10cm2with provisions for recordingeach.3.1.20 total effectiv
37、e dose equivalent (TEDE), nthe sumof the deep dose equivalent (for external exposures) and thecommitted effective dose equivalent (for internal exposures).3.1.21 transient worker, na worker who has work assign-ments at two or more different nuclear facilities within onecalendar year. This may or may
38、 not involve a change inemployer.3.1.22 vital area, nan area of a nuclear facility thatcontains any equipment, system, or device, the failure ordestruction of which could directly or indirectly endangerpublic health and safety by exposure to radiation.3.1.23 whole body dose, nincludes the external d
39、eep doseto the head and trunk, active blood-forming organs, includinggonads, and the elbows and arms above the elbow, or the kneesand legs above the knee.3.1.23.1 DiscussionThe NRC (10CFR20.1003) includesthe knees and elbows with the extremities.4. Significance and Use4.1 The standardization of nucl
40、ear facility transient workerrecords will provide the individual transient worker with agreater assurance that the radiation doses that may be receivedare within regulatory limits.4.2 This specification establishes a fixed content for nuclearfacility transient worker records. Standardizing the conte
41、nt ofthese records will facilitate the establishment of an industry-wide record keeping system.4.3 The standardization of nuclear facility transient workerrecords will reduce the time required for in-processing of theseworkers.5. Content of Nuclear Facility Transient WorkerRecordsThe following forma
42、t for recording dates to facilitate entryinto electronic information systems is recommended:DDAAAYYYY (day2 digits; month3 alphabetic; year4digits).5.1 Worker Identification Data Element:5.1.1 Namelast, first, and middle initial, as applicable.5.1.2 Identification code (such as a social security num
43、beror passport number).5.1.3 Date of birth.5.1.4 Permanent address.5.1.5 Verification that the data contained in the workersrecord have been reviewed by the worker and are complete tothe best of the workers knowledge as of the verification date.5.1.6 Date of verification.5.2 Occupational External Ra
44、diation Exposure Data Ele-ments:5.2.1 Current calendar year occupational external radiationexposure data element shall include the following informationfor each employer during the current calendar year (see Note3):5.2.1.1 Name of employer,5.2.1.2 Address of employer,5.2.1.3 Period of exposure (from
45、 - to),5.2.1.4 Name and address of nuclear facility for the periodof exposure (see 5.2.1.3),5.2.1.5 Deep dose equivalent for the period of exposure (see5.2.1.3),5.2.1.6 Shallow dose equivalent for the skin of the wholebody for the period of exposure (see 5.2.1.3 and 3.1.19),5.2.1.7 Shallow dose equi
46、valent for the skin of the extremityreceiving the maximum dose for the period of exposure (see5.2.1.3, 3.1.19, and 3.1.23),5.2.1.8 Eye dose equivalent to the lens of the eye for theperiod of exposure (see 5.2.1.3), and5.2.1.9 Total effective dose equivalent for the period ofexposure (see 5.2.1.3).5.
47、2.1.10 For each of the doses identified in 5.2.1.5-5.2.1.9,specify whether the entry is an official record dose or anestimated dose.5.2.2 At the end of the current calendar year the whole bodydose information will be transferred to the lifetime radiationexposure history data element (see 5.4).NOTE 3
48、The amount of worker external radiation exposure data that iskept on file at a nuclear facility greatly exceeds that required by dataelement 5.2.1 (for example, radiation type, dosimeter type, or dosimeterlocation on the body (see ANSI N13.6). This level of detail is not,however, required for record
49、s to be used for in-processing of transientworkers.5.3 Occupational Internal Radiation Exposure Data Ele-ment:5.3.1 The committed dose equivalent (CDE) shall be deter-mined for each organ affected by a radiation source locatedinside the body.5.3.2 Data should be recorded to assist in the dose determi-nation and should include, as a minimum, the following:5.3.2.1 Radionuclide,5.3.2.2 Inhalation class (if applicable),5.3.2.3 Mode of intake,5.3.2.4 Intake amount,5.3.2.5 Date of intake, if known, and5.3.2.6 Form of radionuclide (for example, oxid
