1、Designation: E 1034 95 (Reapproved 2008)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 confront
6、ing 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 responsi
8、bility 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-proc
9、essing 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. Th
11、is 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 u
12、sed 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 n
13、uclear 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 referenc
14、es in this specification to licensee, the U.S. NRC Regulatory1This specification is under the jurisdiction of ASTM Committee E10 onNuclear Technology and Applications and is the direct responsibility of Subcom-mittee E10.03 on Radiological Protection for Decontamination and Decommission-ing of Nucle
15、ar Facilities and Components.Current edition approved Jan. 1, 2008. Published February 2008. Last previousedition approved in 2001 as E 1034-95(01).1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.Guides, and Title 10 of the U.S. Code
16、 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 needed for in-processing of nuclear facilitytransient workers.NOTE 2This specification does not defi
17、ne the form of the requiredworker records (such as a passport or central computerized record keepingsystem).2. Referenced Documents2.1 ASTM Standards:2E 1168 Guide for Radiological Protection Training forNuclear Facility Workers2.2 ANSI Standards:ANSI N13.6 American National Standard Practice for Oc
18、-cupational 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/CR-0041, Manual of Respiratory
19、ProtectionAgainst Airborne 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 Insu
20、rance 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 un
21、it of 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 tissue
22、s of 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
23、. It 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 no
24、t the 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 i
25、n tissue, 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 concer
26、n that 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 DiscussionEsti
27、mated 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 t
28、he elbow 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
29、.1.13 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.
30、1.14 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 radioac
31、tivematerials (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
32、 resulting 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).2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Cust
33、omer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org4Available from the Supe
34、rintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.5Available from American Nuclear Insurers, 95 Glasterburg Boulevard, Suite300, Glasterburg, CT 06033-453.E 1034 95 (2008)23.1.17 radiation, nin the context of this specification,“radiation” refers to ionizing radiation. Io
35、nizing 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 radiatio
36、n.3.1.19 shallow dose equivalent (SDE), ndose equivalentdelivered 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 include provisions for assessing nonuniformexposures of th
37、e 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 effective dose equivalent (TEDE), nthe sumof the deep dose equivale
38、nt (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 not involve a change inemployer.3.1.22 vital area, nan are
39、a 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 deep doseto the head and trunk, active blood-forming organs,
40、 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 nuclear facility transient workerrecords will provide the indiv
41、idual 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 content ofthese records will facilitate interfacing with industr
42、y-widerecord keeping systems, such as the Nuclear Energy Institute(NEI) Personnel Data System (PADS).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
43、 format 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 securi
44、ty numberor 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 Exter
45、nal Radiation 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
46、 (from - 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 dos
47、e equivalent 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
48、.3).5.2.1.10 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).
49、NOTE 3The 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 records 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
