ASTM E1034-1995(2013) 9375 Standard Specification for Nuclear Facility Transient Worker Records《核设施工人瞬时记录的标准规范》.pdf
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1、Designation: E1034 95 (Reapproved 2013)Standard Specification forNuclear Facility Transient Worker Records1This standard is issued under the fixed designation E1034; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last
2、revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () 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 adeq
3、uately 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 tr
4、ansient 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 wor
5、ker 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 confronting
6、 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 to
7、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 responsibil
8、ity 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-process
9、ing 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 to
10、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. This
11、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 used
12、 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 nucl
13、ear 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 of1This specification is under the jurisdiction of ASTM Committee E10 onNuclear Techn
14、ology and Applicationsand is the direct responsibility of Subcommit-tee E10.03 on Radiological Protection for Decontamination and Decommissioningof Nuclear Facilities and Components.Current edition approved Jan. 1, 2013. Published January 2013. Last previousedition approved in 2008 as E1034-95(2008)
15、. DOI: 10.1520/E1034-95R13.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1the U.S. Department of Defense (DOD) or individual agreement states.The references in this specification to licensee, the U.S. NRC RegulatoryGuides, and Title
16、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 needed for in-processing of nuclear facilitytransient workers.NOTE 2This specific
17、ation does not define the form of the requiredworker records (such as a passport or central computerized record keepingsystem).2. Referenced Documents2.1 ASTM Standards:2E1168 Guide for Radiological Protection Training forNuclear Facility Workers2.2 ANSI Standards:ANSI N13.6 American National Standa
18、rd Practice for Oc-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, Manu
19、al of Respiratory ProtectionAgainst Airborne Radioactive Materials42.4 CFR Documents:Notices, Instructions, and Reports to Workers; Inspections,10CFR, Part 194Standards for ProtectionAgainst Radiation, 10CFR, Part 2042.5 American Nuclear Insurers Documents:ANI/MAELU Information Bulletin 80-1A, Nucle
20、ar LiabilityInsurance Records Retention53. Terminology3.1 Definitions 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 Disc
21、ussionThe SI unit of absorbed dose is the gray(Gy), equal to 1 J/kg (10,000 ergs/g). The traditional unit ofabsorbed 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), n dose equiva-lent t
22、o organs or tissues of reference that will be received froman intake 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 it
23、s weighting factor. 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 Li
24、-censees. It is not 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 p
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