ASTM E1034-1995(2001) Standard Specification for Nuclear Facility Transient Worker Records《核设施工人瞬时记录》.pdf
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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
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