ASTM_E_2215_-_15.pdf

Designation:E221515Standard Practice forEvaluation of Surveillance Capsules from Light-WaterModerated Nuclear Power Reactor Vessels1This standard is issued under the fixed designation E2215;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year 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 practice covers the evaluation of test specimensand dosimetry from light water moderated nuclear powerreactor pressure vessel surveillance capsules.1.2 Additionally,this practice provides guidance on reas-sessing withdrawal schedule for design life and operationbeyond design life.1.3 This practice is one of a series of standard practices thatoutline the surveillance program required for nuclear reactorpressure vessels.The surveillance program monitors theirradiation-induced changes in the ferritic steels that comprisethe beltline of a light-water moderated nuclear reactor pressurevessel.1.4 This practice along with its companion surveillanceprogram practice,Practice E185,is intended for application inmonitoring the properties of beltline materials in any light-water moderated nuclear reactor.21.5 Modifications to the standard test program and supple-mental tests are described in Guide E636.1.6 The values stated in SI units are to be regarded as thestandard.The values given in parentheses are for informationonly.2.Referenced Documents2.1 ASTM Standards:3A370 Test Methods and Definitions for Mechanical Testingof Steel ProductsE8/E8M Test Methods for Tension Testing of Metallic Ma-terialsE21 Test Methods for Elevated Temperature Tension Tests ofMetallic MaterialsE23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE170 Terminology Relating to Radiation Measurements andDosimetryE185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE208 Test Method for Conducting Drop-Weight Test toDetermine Nil-Ductility Transition Temperature of Fer-ritic SteelsE509 Guide for In-Service Annealing of Light-Water Mod-erated Nuclear Reactor VesselsE636 Guide for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels,E 706(IH)E693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements PerAtom(DPA),E 706(ID)E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance,E 706(IIC)E853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance ResultsE900 Guide for Predicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel MaterialsE1214 Guide for Use of Melt Wire Temperature Monitorsfor Reactor Vessel Surveillance,E 706(IIIE)E1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture ToughnessE1921 Test Method for Determination of ReferenceTemperature,To,for Ferritic Steels in the TransitionRange2.2 ASME Standards:4Boiler and Pressure Vessel Code,Section III SubarticleNB-2000,Rules for Construction of Nuclear FacilityComponents,Class 1 Components,MaterialsBoiler and Pressure Vessel Code,Section XI NonmandatoryAppendix A,Analysis of Flaws,and Nonmandatory Ap-pendix G,Fracture Toughness Criteria for Protectionagainst Failure1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved June 1,2015.Published July 2015.Originally approvedin 2002.Last previous edition approved in 2010 as E221510.DOI:10.1520/E2215-15.2Prior to the adoption of these standard practices,surveillance capsule testingrequirements were only contained in Practice E185.3For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.4Available fromAmerican Society of Mechanical Engineers,Third ParkAvenue,New York,NY 10016.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 3.Terminology3.1 Definitions:3.1.1 base metalas-fabricated plate material or forgingmaterial other than a weld or its corresponding heat-affected-zone(HAZ).3.1.2 beltlinethe irradiated region of the reactor vessel(shell material including weld seams and plates or forgings)that directly surrounds the effective height of the active core.Note that materials in regions adjacent to the beltline maysustain suficient neutron damage to warrant consideration inthe selection of surveillance materials.3.1.3 Charpy transition temperature curvea graphic orcurve-fitted presentation,or both,of absorbed energy,lateralexpansion,or fracture appearance as a function of testtemperature,extending over a range inclu