ASTM E1893-08a

Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls

SIGNIFICANCE AND USE
The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

General Information

• Status: Historical
• Publication Date: 31-Oct-2008
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components

Relations

• Replaces: ASTM E1893-08 - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Nov-2008
• Referred By: ASTM E2216-02(2020) - Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
• Effective Date: 01-Nov-2008
• Referred By: ASTM E2420-15(2021) - Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1281-15(2021) - Standard Guide for Nuclear Facility Decommissioning Plans
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1760-16 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1167-15(2021) - Standard Guide for Radiation Protection Program for Decommissioning Operations
• Effective Date: 01-Nov-2008

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E1893 − 08a
StandardGuide for
Selection and Use of Portable Radiological Survey
Instruments for Performing In Situ Radiological
Assessments to Support Unrestricted Release from Further
1
Regulatory Controls
This standard is issued under the fixed designation E1893; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 1.6 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
1.1 This standard provides recommendations on the selec-
standard.
tion and use of portable instrumentation that is responsive to
levels of radiation that are close to natural background. These
2. Referenced Documents
instruments are employed to detect the presence of residual
2
radioactivity that is at, or below, the criteria for release from
2.1 ASTM Standards:
further regulatory control of a component to be salvaged or
C998Practice for Sampling Surface Soil for Radionuclides
reused, or a surface remaining at the conclusion of decontami-
C999Practice for Soil Sample Preparation for the Determi-
nation and/or decommissioning.
nation of Radionuclides
C1000Test Method for Radiochemical Determination of
1.2 The choice of these instruments, their operating charac-
Uranium Isotopes in Soil by Alpha Spectrometry
teristics and the protocols by which they are calibrated and
usedwillprovideadequateassurancethatthemeasurementsof C1133Test Method for Nondestructive Assay of Special
Nuclear Material in Low-Density Scrap and Waste by
theresidualradioactivitymeettherequirementsestablishedfor
release from further regulatory control. Segmented Passive Gamma-Ray Scanning
E170Terminology Relating to Radiation Measurements and
1.3 Thisstandardisapplicabletotheinsitumeasurementof
Dosimetry
radioactive emissions that include:
E181Test Methods for Detector Calibration andAnalysis of
1.3.1 alpha
Radionuclides
1.3.2 beta (electrons)
C1215Guide for Preparing and Interpreting Precision and
1.3.3 gamma
Bias Statements in Test Method Standards Used in the
1.3.4 characteristic x-rays
Nuclear Industry
1.3.5 Themeasurementofneutronemissionsisnotincluded
2.2 ANSI Standards:
as part of this standard.
ANSI N323BRadiation Protection InstrumentationTest and
1.4 This standard dose not address instrumentation used to
Calibration, Portable Survey Instrumentation for Near
3
assess residual radioactivity levels contained in air samples,
Background Operation
surface contamination smears, bulk material removals, or
ANSIN42.17APerformanceSpecificationsforHealthPhys-
half/whole body personnel monitors.
ics Instrumentation-Portable Instrumentation for Use in
3
Normal Environmental Conditions
1.5 Thisstandarddoesnotaddressrecordsretentionrequire-
ANSIN42.17CPerformanceSpecificationsforHealthPhys-
ments for calibration, maintenance, etc. as these topics are
ics Instrumentation-Portable Instrumentation for Use in
considered in several of the referenced documents.
3
Extreme Environmental Conditions
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
2
Technology and Applications and is the direct responsibility of Subcommittee For referenced ASTM standards, visit the ASTM website, www.astm.org, or
E10.03 on Radiological Protection for Decontamination and Decommissioning of contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Nuclear Facilities and Components. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Nov. 1, 2008. Published March 2009. Originally the ASTM website.
3
approved in 1997. Last previous edition approved in 2008 as E1893-08. DOI: Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
10.1520/E1893-08A. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1893 − 08a
2.3 National Council on Radiation Protection and Measure- 3.3 calibration source, n—asusedinthisstandardguide,see
ments: certified reference material.
NCRPReportNo.57InstrumentationandMonitoringMeth-
3.4 certified reference material, n—a material that has been
ods for Radiation Protection, National Council on Radia-
characterizedbyarecognizedstandardortestinglaboratoryfor
4
tion Protection and Measurements, May 1978
someofitschemicalorphysicalorradiologicalproperties,and
NCRP Report No. 58A Handbook of Radioactivity Mea-
that is generally used for calibration of a measurement system
surement Procedures, National Council on Radiation Pro-
or fo
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E 1893–08 Designation:E 1893–08a
Standard Guide for
Selection and Use of Portable Radiological Survey
Instruments for Performing In Situ Radiological
Assessments to Support Unrestricted Release from Further
1
Regulatory Controls
This standard is issued under the fixed designation E 1893; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels
of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity
that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface
remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will
provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from
further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface
contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are
considered in several of the referenced documents.
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
2. Referenced Documents
2
2.1 ASTM Standards:
C 998 Practice for Sampling Surface Soil for Radionuclides
C 999 Practice for Soil Sample Preparation for the Determination of Radionuclides
C 1000 Test Method for Radiochemical Determination of Uranium Isotopes in Soil by Alpha Spectrometry
C 1133 Test Method for Nondestructive Assay of Special Nuclear Material in Low-Density Scrap and Waste by Segmented
Passive Gamma-Ray Scanning
E 170 Terminology Relating to Radiation Measurements and Dosimetry
E 181 Test Methods for Detector Calibration and Analysis of Radionuclides
C 1215 Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in the Nuclear
Industry
2.2 ANSI Standards:
ANSIN323B RadiationProtectionInstrumentationTestandCalibration,PortableSurveyInstrumentationforNearBackground
3
Operation
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.03 on
Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.
Current edition approved JuneNov. 1, 2008. Published July 2008.March 2009. Originally approved in 1997. Last previous edition approved in 20032008 as
E1893-97(2003).E 1893-08.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3 th
American National Standards Institute, 11 W. 42nd St., 13 Floor, New York, NY 10036
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 1893–08a
ANSI N42.17A Performance Specifications for Health Physics Instrumentation-Portable Instrumentation for Use in Normal
3
Environmental Conditions
ANSI N42.17C Performance Specifications for Health Physics Instrumentation-Portable Instrumentation for Use in Extreme
3
Environmental Conditions
2.3 National Council on Radiation Protection and Measurements:
NCRP Report No. 57 Instrumentation and Monitoring Methods for Radiation Protection, National Council on Radiation
4
Protection and Measurements, May 1978
NCRP Report No. 58 A Handbook of Radioactivity Measurement Procedures, National Council on Radiation Protection and
4
Measu
...