1、Designation:C99397(Reapproved 2012)Standard Guide forIn-Plant Performance Evaluation of Automatic PedestrianSNM Monitors1This standard is issued under the fixed designation C993;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the yea
2、r of last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon()indicates an editorial change since the last revision or reapproval.1.Scope1.1 This guide is affiliated with Guide C1112 on applyingspecial nuclear material(SNM)monitors,Guide C1169 onlaboratory pe
3、rformance evaluation,Guide C1189 on calibrat-ing pedestrian SNM monitors,and Guides C1236 and C1237on in-plant evaluation.This guide to in-plant performanceevaluation is a comparatively rapid way to verify whether apedestrian SNM monitor performs as expected for detectingSNM or SNM-like test sources
4、.1.1.1 In-plant performance evaluation should not be con-fused with the simple daily functional test recommended inGuide C1112.In-plant performance evaluation takes place lessoften than daily tests,usually at intervals ranging from weeklyto once every three months.In-plant evaluations are also moree
5、xtensive than daily tests and may examine both a monitorsnuisance alarm record and its detection sensitivity for aparticular SNM or alternative test source.1.1.2 In-plant performance evaluation also should not beconfused with laboratory performance evaluation.In-plantevaluation is comparatively rapi
6、d,takes place in the monitorsroutine operating environment,and its results are limited toverifying that a monitor is operating as expected,or todisclosing that it is not and needs repair or recalibration.1.2 In-plant evaluation is one part of a program to keepSNM monitors in proper operating conditi
7、on.Every monitor ina facility is evaluated.There are two applications of thein-plant evaluation:one used during routine operation andanother used after calibration.1.2.1 Routine Operational EvaluationIn this form of theevaluation,nuisance alarm records for each monitor areexamined,and each monitors
8、detection sensitivity is estimatedduring routine operation.The routine operational evaluation isintended to reassure the plant operator,and his regulatoryagency,that the monitor is performing as expected duringroutine operation.This evaluation takes place without pre-testing,recalibration,or other a
9、ctivity that might change themonitors operation,and the evaluation simulates the normaluse of the monitor.1.2.2 Post-Calibration EvaluationThis form of the evalu-ation is part of a maintenance procedure;it should alwaysfollow scheduled monitor recalibration,or recalibration con-nected with repair or
10、 relocation of the monitor,to verify that anexpected detection sensitivity is achieved.Nuisance alarm datado not apply in this case because the monitor has just beenrecalibrated.Also,having just been calibrated,the monitor islikely to be operating at its best,which may be somewhat betterthan its rou
11、tine operation.1.3 The values stated in SI units are to be regarded asstandard.1.4 This standard does not purport to address the safetyproblems,if any,associated with its use.It is the responsibilityof the user of this standard to establish appropriate safety andhealth practices and determine the ap
12、plicability of regulatorylimitations prior to use.2.Referenced Documents2.1 The guide is based on ASTM standards that describeapplication and evaluation of SNM monitors,as well astechnical publications that describe aspects of SNM monitordesign and use.2.2 ASTM Standards:2C859 Terminology Relating t
13、o Nuclear MaterialsC1112 Guide for Application of Radiation Monitors to theControl and Physical Security of Special Nuclear Material(Withdrawn 2014)3C1169 Guide for Laboratory Evaluation of Automatic Pe-destrian SNM Monitor PerformanceC1189 Guide to Procedures for Calibrating Automatic Pe-destrian S
14、NM MonitorsC1236 Guide for In-Plant Performance Evaluation of Auto-matic Vehicle SNM Monitors(Withdrawn 2014)31This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.12 on SafeguardApplications.Current edition approved Jan
15、.1,2012.Published January 2012.Originallyapproved in 1991.Last previous edition approved in 1997 as C993 97(2003).DOI:10.1520/C0993-97R12.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume info
16、rmation,refer to the standards Document Summary page onthe ASTM website.3The last approved version of this historical standard is referenced onwww.astm.org.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 C1237 Guide to In-Plant Performance Evaluation of Hand-Held SNM Monitors(Withdrawn 2014)33.Terminology3.1 Definitions:3.1.1 alternative test sourcealthough no other radioactivematerials individually or collectively duplicate the radio
