Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within the Nuclear Industry (Withdrawn 2005)

SCOPE
1.1 This standard provides guidance for establishing and maintaining a measurement system quality control program. Guidance is provided for general program considerations, preparation of quality control samples, analysis of quality control samples, quality control data analysis, analyst qualification, measurement system calibration, measurement method qualification, and measurement system maintenance.
WITHDRAWN RATIONALE
This standard provides guidance for establishing and maintaining a measurement system quality control program.
Formerly under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle, this guide was withdrawn in May 2005 in accordance with the Regulations Governing ASTM Technical Committees, which requires that standards shall be updated by the end of the eighth year since the last approval date.

General Information

Status
Historical
Publication Date
31-Dec-1995
Withdrawal Date
29-Jun-2005
Current Stage
Ref Project

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ASTM C1210-96e1 - Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within the Nuclear Industry (Withdrawn 2005)
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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
e1
Designation: C 1210 – 96
Standard Guide for
Establishing a Measurement System Quality Control
Program for Analytical Chemistry Laboratories Within the
1
Nuclear Industry
This standard is issued under the fixed designation C 1210; 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 (e) indicates an editorial change since the last revision or reapproval.
1
e NOTE—Editorial changes were made throughout in March 1997.
1. Scope C 1297 Guide for Laboratory Analysts for the Analysis of
2
Nuclear Fuel Cycle Materials
1.1 This standard provides guidance for establishing and
2.2 ISO Standard:
maintaining a measurement system quality control program.
ISO Guide 30 Terms and Definitions Used in Connection
Guidance is provided for general program considerations,
3
with Reference Materials
preparation of quality control samples, analysis of quality
2.3 ANSI Standards:
control samples, quality control data analysis, analyst qualifi-
ANSI/ASQC B1 Guide for Quality Control Charts
cation, measurement system calibration, measurement method
ANSI/ASQC B2 Control Chart Method of Analyzing Data
qualification, and measurement system maintenance.
ANSI/ASQC B3 Control Chart Method of Controlling
1.2 This guidance is provided in the following sections:
Quality During Production
Section
General Quality Control Program Considerations 5
3. Terminology
Quality Control Samples 6
Analysis of Quality Control Samples 7
3.1 Definitions of Terms Specific to This Standard:
Quality Control DataAnalysis 8
3.1.1 calibration—the determination of the values of the
Analyst Qualification 9
Measurement System Calibration 10
significant parameters by comparison with values indicated by
Measurement Method Qualification 11
a reference instrument or by a set of reference standards.
Measurement System Maintenance 12
3.1.2 calibration curve—the graphical or mathematical rep-
2. Referenced Documents
resentationofarelationshipbetweenameasuredparameterand
a property of the standard for the substance under consider-
2.1 ASTM Standards:
2
ation.
C 859 Terminology Relating to Nuclear Materials
3.1.3 calibration factor—the slope of the calibration curve,
C 986 Guide for Developing Training Programs in the
2
or its inverse for a linear calibration curve.
Nuclear Fuel Cycle
3.1.4 calibration standard—any of the standards of various
C 1009 Guide for Establishing a Quality Assurance Pro-
types having accepted values for parameters of interest.
gram for Analytical Chemistry Laboratories Within the
2
3.1.4.1 Discussion—The calibration standard may be used
Nuclear Industry
to adjust the sensitivity of test instruments at some predeter-
C 1068 Guide for Qualification of Measurement Methods
2
mined level and for periodic checks of the sensitivity.
by a Laboratory Within the Nuclear Industry
3.1.5 calibration verification—the action taken to verify the
C 1128 Guide for Preparation of Working Reference Mate-
continued validity of calibration during a time period between
rials for Use in the Analysis of Nuclear Fuel Cycle
2
calibrations.
Materials
3.1.5.1 Discussion—Verification involves less rigor and ef-
C 1156 Guide for Establishing Calibration for a Measure-
fort than full calibration and involves analyzing a standard at a
ment Method Used to Analyze Nuclear Fuel Cycle Mate-
2
specified frequency during the calibration period. Verification
rials
couldinvolveusingastandardthatislowerthanthecalibration
standard in the metrological hierarchy of standards.
3.1.6 certified reference material (CRM)—a reference ma-
1
This guide is under the jurisdiction ofASTM Committee C-26 on Nuclear Fuel
terial one or more of whose property values are certified by a
CycleandisthedirectresponsibilityofSubcommitteeC26.08onQualityAssurance
Applications.
Current edition approved Dec. 10, 1996. Published February 1997. Originally
3
published as C 1210 – 91. Last previous edition C 1210 – 91. Available from American National Standards Institute, 11 West 42nd Street,
2
Annual Book of ASTM Standards, Vol 12.01. 13th Floor, New York, NY 10036.
Copyright ©ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA19428-2959, United States.
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C 1210
technically valid procedure, accompanied by or traceable to a
certificate or other documentation which is issued by a certi-
fying body (see ISO Guide 30).
3.1.6.1 Discussion—Acertifying body is a technically com-
petent body (organization or firm, public or private) that issues
a reference material certificate (see ISO Guide 30). Such an
organization could be the National Institute of Standards and
Technology (NIST) or the New Brunswick Laboratory.
3.1.6.2 Discussio
...

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