ASTM International Roadmap in Support of Commercial ... By the late 1990s there was a broad-based initiative underway in the commercial nuclear power industry to resolve longstanding

Background

By the late 1990s there was a broad-based initiative underway in the

commercial nuclear power industry to resolve longstanding technical issues

and to identify gaps in existing technology. The driver was to pave the way for

license renewal of the operating plants to assure safe operation for as long as

could reasonably be demonstrated. The focus was on establishing the basis

for regulations, codes and standards needed to manage aging nuclear power

plant components. The motivation was to achieve regulatory stability through

proactive inspections and analyses to minimize the type of surprises that might

impact the future of the commercial nuclear power industry.

ASTM International Roadmap in Support of Commercial Nuclear Power

A S T M S T A n d A r d S : r o A d M A p i n S u p p o r T o f c o M M e r c i A l n u c l e A r p o w e r w w w . a s t m . o r g

Background conTinued The U.S. Department of Energy (DOE) identified the specific

need to update citations to standards in the U.S. Nuclear Regulato-ry Commission (NRC) regulations. DOE has numerous advanced concepts (Generation IV nuclear plant designs, for example) and needed a forum for getting that information to the Standards De-velopment Organizations (SDOs) so that action could be managed to update citations to standards in NRC regulations. One example pertains to “ceramics in high temperature gas reactors;” this could involve ASTM, ANS and other SDOs. In 2008, the Nuclear EnergyStandards Coordination Collaborative (NESCC) was initiatedby the DOE and the American National Standards Institute (ANSI). NESCC was organized to support the standardization effort for operating plants as well as to extend the scope to support the design and construction of new nuclear plants. NESCC would contribute through actions by the codes and SDOs in concert with the NRC. The NRC was involved for two reasons: (1) codes and standards are cited in many of the agency’s documents (regulations,regulatory guides, standard review plans and technical publica-tions); and (2) NRC is required to consider existing codes and standards if available and viable for the intended application. As an SDO, ASTM International is a key part of the NESCC initiative.

PurPose of The asTM inTernaTional roadMaP

This roadmap serves as a plan to help identify actions specific to ASTM; to help prioritize, manage and delegate those actions to

relevant ASTM technical committees; and to help measure progress with respect to the overall goals of the plan. The roadmap is to be a living document, in that it will be maintained and updated as appropriate, given completion of specific actions, identification of new actions or activities, and efforts by other members and stake-holders associated with NESCC.

This roadmap identifies top priorities and opportunities in the commercial nuclear energy sector that: • Encompass the objectives of NESCC Task Group on Standards

Prioritization; • Build on the results of the ASTM nuclear survey and Nuclear

Standards Workshop (described further in this roadmap); and• Manage gaps in the underlying technology and standards based

on their significance to the NESCC goals.

The roadmap is of importance to ASTM International because it provides: • The formation of a self-sustaining nuclear energy focal point

within ASTM; • The strengthening of alliances with other societies and

international organizations; • An increased understanding of the nuclear energy sector and

how to effectively contribute to this industry through the actions of ASTM technical committees; • The identification of gaps in current and emerging technologies

and related standards; and• The development of a comprehensive Web-based clearinghouse

of nuclear energy information.

PoTenTial coMMunicaTion PaThs

NESCC – As an active member of NESCC, ASTM International meets regularly with representatives from other member organizations. The meetings are a means to communicate directly with other members and learn of their activities, and to discuss opportunities for collaboration in support of NESCC goals.

Symposia and Workshops – ASTM International is in an ideal position to sponsor symposia and workshops through its various technical committees. ASTM can effectively collaborate with other SDOs, industry groups and NRC to conduct symposia and workshops.

w w w . a s t m . o r g A S T M S T A n d A r d S : r o A d M A p i n S u p p o r T o f c o M M e r c i A l n u c l e A r p o w e r

Such forums can include representatives from academia, which will secure participants with specialized expertise. Workshops have been used effectively for certification and training.

ASTM Nuclear Portal – The portal is a gateway of data to all nuclear-related aspects within ASTM and is useful for other organizations (EPRI, ASME, ANS), nuclear plant owners groups and academia. Potential collaboration may develop from this portal in the form of coordinating activities, sponsoring events and pinpointing technology gaps. ASTM Online Collaboration Areas – This tool on the ASTM website allows for group participation (ASTM membership not required) in creating new standards and revising existing ones. Currently a collaboration area has been created by a task group within Subcommittee E10.02 on Behavior and Use of Nuclear Structural Materials to communicate proposed changes to ASTM E900, Standard Guide for Predicting Radiation-Induced Transi-tion Temperature Shift in Reactor Vessel Materials, E706 (IIF). This is an excellent communication tool that can be shared by academics, standards users, regulators, researchers and other SDOs.

inPuTs To The asTMinTernaTional roadMaPASTM Nuclear SurveyIn November 2010, a survey was distributed to preselected committees regarding the importance and status of standards in the nuclear industry. The results of the survey were intended to assist in creating a roadmap to identify top priorities and opportunities in the nuclear energy sector. The survey’s usefulness provided broad exposure to ten committees and yielded a solid overall response. It was augmented by the generation of a report containing ASTM standards that are ref-erenced in NRC Regulations, guides and technical documents. (see Attachment A).

Workshop on “Emerging Trends in Nuclear Energy: TheStandards Component” This workshop was held on June 15, 2011, in Anaheim, Calif. Its stated purpose was: (1) to contribute to the civil nuclear energy section of the ASTM roadmap; (2) to learn more about the NRC perspective on the nuclear industry, i.e., the trends and opportunities that will arise, the issues and priorities that need to be addressed; and (3) to facilitate communication. The pre-senters included representatives from NRC, NIST and ASTM.

near-TerM goals for asTM inTernaTional1 - Discuss with NRC the feasibility to co-sponsor workshops

that address specific topics. Status – discussions in process/topical meetings ongoing. Some of the following topics to becovered at workshops:• Small-Bore Piping – This area of specialized piping is being

reviewed for newer nuclear facilities.

• Pressure-Temperature- Limit Curves for Nozzles – Lim-its on the operation of a nuclear reactor pressure vessel are explicitly determined for the vessel “shell;” given the longer term operation of the vessel, consideration is given to creating methods to explicitly include limits on operation keyed to the primary inlet and outlet nozzles that reflect potential age-related degradation. This subject is multidisciplinary since it involves both the ASME Boiler and Pressure Vessel Code and


ASTM standards on reactor structural materials.• Instrument Calibration – This topic pertains to the methods used to initially calibrate nuclear plant instrumentation as well as methods for managing the age-

related degradation of the instrument, such as timing for inspection of the calibration accuracy over time. This subject is multidisciplinary since it involves NRC Regulations on inspection, ASTM standards on calibration, as well as to-be-determined input on age-related degradation.

• Embrittlement Mechanisms – This topic targets age-related degradation of reactor materials, including both pressure boundary and reactor internals components that will have to function for as many as 80 years. This subject is multidisci-plinary since it involves ASME on inspection requirements, NRC guidance on aging management, ASTM standards on testing and evaluation of reactor structural materials, standards from other SDOs, and to-be-determined input on age-related degradation from various SDOs.

The 2011 asTM nuclear WorkshoPwas a discussion intended to communicate high-level issues and priorities (see bulleted items above and item 2 below). NESCC representatives requested that the ASTM report on the workshop be made available to NESCC. Videos of the proceedings are currently available on the ASTM website in the Nuclear Portal. A link of the proceedings will be accessible via both the ASTM Nuclear Portal and the NESCC main page on the ANSI website.

The September 2011 NRC Workshop was the latest of two recent meetings to discuss implementation needs for a specific NRC regulation (Alternate Pressurized Thermal Shock Rule). The existing schedule is as stated; the specific schedule will be updated as details become available.

At the Nov. 29, 2011, NESCC Meeting, NRC representa-tives requested a copy of the ASTM Roadmap, preferably at an early stage, for review. It will be distributed to appropriate NRC staff for review and comment to ascertain that efforts by NRC and ASTM are coordinated. An action plan was also requested to realize which issues ASTM considers high priority so NRC can determine where the needs are the greatest for assigning resources. 2 - Act on list of ASTM standards referenced in NRC docu-ments, results of ASTM survey and NRC action item list (seeNRC workshop topics) with appropriate ASTM committees involved with standards for the civil nuclear power industry.Examine NRC regulations for citations to ASTM standards to ascertain that citations are appropriate and current. Status:

• Working through appropriate ASTM staff to communicate with relevant committees.

• Assist with direction on prioritization with committees that are currently addressing identified gaps.

• Subcommittee E10.02 held discussions with NRC regarding the use of revisions of ASTM E185, Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels, and ASTM E2215, Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels, in changes to NRC Regulations, 10 CFR 50, Appendix H. The subcom-mittee will prepare a strategy with appropriate NRC represen-tatives on the optimum approach for incorporating revisions to these standards into rulemaking actions. This was discussed at the January 2012 E10.02 meeting and used to prepare a draft plan (see Attachment C).

• Plan to solicit input from other ASTM technical committees. Each committee should provide specific input as to why ac-tion is needed on individual standards in order to communi-cate that need to the NRC and other SDOs as appropriate.

• A prioritized list of standards is being prepared for input to the NESCC task group (see Attachment B). Use of the NESCC task group to communicate needs to other partici-pants will help implement the ASTM Nuclear Roadmap and overcome barriers when encountered.

• NESCC Task Group on Concrete and Rebar may need to consider other aspects of nuclear plant construction (e.g., welding). ASTM will research what might be needed and what roles are to be played.

• Construction of a database by NRC will include citations to standards referenced in the various documents. A request was made to all SDOs for input on citations as well as status with respect to current standard. Some hurdles may exist for power plant licensees to incorporate any standards updates, such as restrictions on back-fitting to protect financial interests.

• NIST has recognized the possible addition of concrete (as well as of many other technical areas) in addressing the ex-tended operating period with respect to inspection scope and frequency of components subject to age-related degradation.

• ASTM will research possible contributions to NESCC’s Elec-trical Cable Task Group. Regulatory Guide 1.218 on electrical cables is to be issued soon to address the Maintenance Rule and Condition Monitoring (10 CFR 50.62); NRC could pos-sibly benefit from an industry standard for cable testing, if available.

• NESCC’s HDPE Piping Task Group may require ASTM expertise on polymeric piping (e.g. D2837, Standard Test Method for Obtaining Hydrostatic Design Basis for Thermo-

october 2012


plastic Pipe Materials or Pressure Design Basis for Thermo-plastic Pipe Products, and D3350, Standard Specification for Polyethlylene Plastics Pipe and Fittng Materials) to ensure this task group is aligned with the ASTM Nuclear Roadmap.

3 - Clarify the roles of ASTM and the American Nuclear Society (ANS) with respect to standards related to nuclear fuel facilities and power plant dismantling and decommissioning. Status:

• Reviewing prior history with respect to ASTM and ANS roles in nuclear fuel technology.

• Working with the chairman of ASTM Committee C26 on Nuclear Fuel Cycle; working with ANS to understand the differences between ASTM and ANS standards in order to map out a course of action by both SDOs. The next step is to establish a plan and specific milestones.

4 - Establish areas for collaboration with Nuclear FabricationConsortium (NFC). Status:

• NFC initiatives have been identified and potential synergies from ASTM/NFC collaboration are being explored.

• SiC Joining for Nuclear Fuel Rods – The objective is to develop a method for joining SiC to itself. The joint must be able to withstand a high neutron flux, operating tem-peratures of 3000C and temperature excursions as high as 14000C. Exploring this topic within ASTM Committees C26, B10 on Reactive and Refractory Metals and Alloys, and E10 on Nuclear Technology and its Applications to determine the most appropriate ASTM resources to employ. Under Committee C26, ASTM C934, Standard Guide for Design and Quality Assurance Practices for Nuclear Fuel Rods is currently not an active standard, but, if necessary, can be reinstated if it meets the needs of NFC. Moreover, Subcom-mittee C26.02 on Fuel and Fertile Material Specifications may have existing standards that would apply to this activ-ity. Committee B10 covers the following principle metals: titanium, zirconium, hafnium, niobium, tantalum, tungsten and molybdenum. Committee E10 has several existing stan-dards in the following subcommittees that would apply to this activity: E10.05 on Nuclear Radiation Metrology; E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices; and E10.08 on Procedures for Neutron Radia-tion Damage Simulation.

• SolGel Corrosive Coatings – The objective is to develop a next generation ceramic-based corrosion coating with the intended purpose of stopping or mitigating stress corrosion cracking in nuclear (and similar) operating environments.

This area is being explored within ASTM Committees C28 on Advanced Ceramics and D33 on Protective Coatings for Power Generation Facilities. Committee C28 has an existing task group that covers ceramic coatings. Committee D33 has jurisdiction over several standards that cover coatings, many of which are referenced by the NRC. The standards from Committees E10 and G01 on Corrosion of Metals may not apply, however, this is still being pursued as more details are

learned about the activity.• High Energy Density Welding of IN690 – The objective is to

evaluate the existing high energy density welding and joining technologies for Alloy 690 for nuclear piping and pressure vessel applications.

• Welding and Machining Technology Demonstration – The objective is to demonstrate what is available to nuclear manu-facturing facilities welding and machining technology. The focus is on technologies that are currently deployed in other industries but have yet to be employed in the nuclear

industry.

ASTM will establish a plan and specific schedule for working


with NFC. An initial list has been shared that identifies recent NFC initiatives and potential responsible ASTM committees. The objective of the plan is to identify to NFC where ASTM expertise exists for each initiative and to offer that expertise if de-termined to be appropriate by the responsible ASTM committee.

5 - Establish areas for collaboration with Electric Power Research Institute (EPRI). Status:Discussions are ongoing with EPRI to explore possible areas of collaboration with the following goals:• Learn about the current EPRI project topics, including the

Advanced Nuclear Technology project.• Discuss how teaming with EPRI could benefit the current

NESCC initiatives. Probe what ASTM might provide to assist in furthering the EPRI project goals in terms of standard-ization needs, e.g., how to quickly plug in EPRI products to ASTM standards actions to expedite the application of technology enhancements.

• Establish a main contact for subsequent interactions to permit identification of current and planned projects to pursue.• Probe into how teaming might be used to promote each

other’s products.

6 - Pursue link with nuclear utilities as resource for evaluatingASTM International Roadmap in terms of actions and priori-

tization. Status:• Efforts are in process to identify potential partners.

This effort is linked to the preceding goal concerning EPRI.Potential partners including likely individuals within those organizations have been identified. If found to be viable, action will be taken to establish a plan and specific schedule for a joint collaboration between ASTM International, EPRI and a nuclear utility.

roadMaP TiMelinesThe approximate schedules (timelines) for each Roadmap item are provided below. Importance to ASTM is indicated by “A” for the highest priority, “B” for important, “C” for follow-up items and “D” for task management items.

• Make available the ASTM Nuclear Workshop report to NE SCC via hyperlink on both organization’s websites. “A”

• Ascertain NRC workshop schedule for discussions on implementation needs for specific NRC regulation and technology areas. “A”• Pending acceptability to ASTM, provide NRC a copy of the ASTM Roadmap for review and comment. “A”• Subcommittee E10.02 discussed at the January 2012 meet-

ing the use of revisions of ASTM standards E185 and E2215 in changes to NRC Regulation 10 CFR 50, Appendix H. The Subcommittee will prepare a draft plan for desired rulemak-ing activity. “A/B”

• Solicit inputs from relevant ASTM technical committees and subcommittees regarding standards action needed, why it is needed, and communicate that need to NRC and other SDOs as appropriate. This is a continuing effort for the duration of the NESCC project. “C”

• Continue efforts on the prioritized list of standards, includ-ing the preparation of updates to the list and transmittal to the NESCC Task Group. The latest available update will be provided to NESCC on an ongoing basis. “C”

• Explore standards spanning both ASTM and ANS, and map out a course of action by both SDOs with specific milestones. “A”• Establish a plan and specific schedule with NFC. An initial

list has been shared that identifies recent NFC initiatives and a potential responsible ASTM committee (C28) for one of the topics. “B”

• Discuss with EPRI the potential for collaboration. If vi-able, action will be taken to establish a plan and specific schedule. “A”

• Pursue a link with nuclear utilities as resource for evaluating the ASTM Roadmap in terms of actions and prioritization. If viable, action will be taken to establish


a plan and specific schedule for a joint collaboration between ASTM, EPRI and a nuclear utility. “A”• On a continuing basis, communicate needs via NESCC to other participants to help implement the ASTM Roadmap

and overcome barriers when encountered. Work with NESCC to minimize hurdles in obtaining SDO inputs to the regulations and encouraging power plant licensees to incorporate updates. “C”• Work with NESCC Task Group on concrete and rebar to also consider other aspects of nuclear plant construction, e.g.,

welding. ASTM and others should look into what might be needed and what roles are to be played. “B”

• Work with NRC regarding newly-constructed database with citations to standards and requested inputs on citations as well as status with respect to current standard. “B”• Work with NESCC regarding addressing the extended operat-

ing period with respect to inspection scope and frequency of components subject to age-related degradation for concrete (as well as to many other technical areas).“B”

• Work with NESCC’s Electrical Cable Task Group to determine what role ASTM can play. “B”

• Work with NRC regarding the pending issue of Regulatory Guide 1.218 on electrical cables to address the Maintenance Rule and Condition Monitoring (10 CFR 50.62). NRC could possibly benefit from an industry standard for cable testing if

available. “B”• Work with NESCC’s HDPE Piping Task Group regarding the

need for ASTM expertise on polymeric piping (e.g. ASTM D2837, ASTM D3350, F28) to ensure the task group and the ASTM roadmap are aligned. “B”

aTTachMenTs[A] ASTM standards cited in NRC documents[B] Prioritized list of ASTM standards for NESCC[C] Action Plans for the Nuclear Industry

conTacT:Joe Koury, ASTM [email protected].

ASTM meetings are FREE to attend and are open to non-members. For information on upcoming ASTM committee meetings, visit www.astm.org/MEETINGS,or contact Joe Koury ([email protected]).

To download a PDF of the Nuclear Roadmap and see other ASTM nuclear-related information, visit:

www.astm.org/portals/nuclear

aBouT asTMASTM International is a globally recognized leader in the development and delivery of international voluntary consensus standards. Today, some 12,000 ASTM standards are used around the world to improve product quality, enhance safety, facilitate market access and trade, and build consumer confidence. ASTM International meets the World Trade Organization (WTO) principles for the development of international standards: coherence, consensus, development dimension, effectiveness, impartiality, openness, relevance and transparency.


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ASTM STANDARDS REFERENCED IN NRC REGULATORY GUIDES

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!RI+),"#(-#.-),/'$010$#"02()12.)9.'$0/0"#"02(D,".'(N"%'('-)O2PD=#.>2()M0$B'4D=2//'.D=%.2&07&DK24L>-'(7&D=247&>07&)!442L),".7$"7.#4),"''4)94#"'8)

!R**),"#(-#.-),/'$010$#"02()12.)Y($2#"'-)C0N%D,".'(N"%),"''4)A#.8)12.)9.'8".'880(N)=2($.'"')

!R;<),"#(-#.-),/'$010$#"02()12.)9.'887.'):'88'4)94#"'8@)O2PD=#.>2()!N'DC#.-'(0(N)M0$B'4D=2//'.D=%.2&07&DK24L>-'(7&D=247&>07&)#(-)M0$B'4D=2//'.DK#(N#('8'DK24L>-'(7&D=247&>07&)!442L),"''4)


!""#$%&'(")!))

!RJ;),"#(-#.-),/'$010$#"02()12.)=#8"0(N8@)Q.2(D=%.2&07&@)Q.2(D=%.2&07&DM0$B'4@)=2..2802()5'808"#("@)12.)3'('.#4)!//40$#"02()

!R?W),"#(-#.-),/'$010$#"02()12.)=#.>2(),"''4)=.#(')5#048)

!R<R),"#(-#.-),/'$010$#"02()12.)F0($D=2#"'-)]3#4T#(0V'-^),"''4)A#.8)12.)=2($.'"')5'0(12.$'&'(")

!RW?),"#(-#.-),/'$010$#"02()12.)A4#$B)#(-)C2"DE0//'-)F0($D=2#"'-)]3#4T#(0V'-^)G'4-'-)#(-),'#&4'88),"''4)90/')12.)U0.')9.2"'$"02()Y8')

))

COMMITTEE A04 ON IRON CASTINGS

!?RI),"#(-#.-),/'$010$#"02()12.)!78"'(0"0$)E7$"04')Q.2()=#8"0(N8)12.)9.'887.'D=2("#0(0(N)9#."8),70"#>4')12.)O2PDS'&/'.#"7.'),'.T0$')

!HRJ),"#(-#.-),/'$010$#"02()12.)U'..0"0$)E7$"04')Q.2()=#8"0(N8),70"#>4')12.)O2PDS'&/'.#"7.'),'.T0$')

))

COMMITTEE B02 ON NONFERROUS METALS AND ALLOYS

AW;*),"#(-#.-),/'$010$#"02()12.)O2PD=#.>2()M0$B'4D=%.2&07&DK24L>-'(7&D3#-240(07&)!442L)94#"'@),%''"@)#(-),".0/)

)COMMITTEE B05 ON COPPER AND COPPER ALLOYS

A**),"#(-#.-),/'$010$#"02()12.)A.2(V')=#8"0(N8)12.)A.0-N'8)#(-)S7.("#>4'8)

A<I),"#(-#.-),/'$010$#"02()12.),"'#&)2.):#4T')A.2(V')=#8"0(N8)

AI?I),"#(-#.-),/'$010$#"02()12.)=2//'.DM0$B'4DF0($)!442L)]M0$B'4),04T'.^)#(-)=2//'.DM0$B'4)52-)#(-)A#.)

A*RI),"#(-#.-),/'$010$#"02()12.)=2//'.DA#8')!442L)='(".017N#4)=#8"0(N8)

A;?W),"#(-#.-),/'$010$#"02()12.)=2//'.)#(-)=2//'.D!442L),'#&4'88)=2(-'(8'.)#(-)C'#")_`$%#(N'.)S7>'8)P0"%)Q("'N.#4)U0(8)

)


!""#$%&'(")!))

COMMITTEE B07 ON LIGHT METALS AND ALLOYS

A??R),"#(-#.-)S'8")K'"%2-8)12.)S'(802()S'8"0(N)G.27N%")#(-)=#8")!47&0(7&D)#(-)K#N('807&D!442L)9.2-7$"8)

)COMMITTEE B08 ON METALLIC AND

INORGANIC COATINGS

A<;;),"#(-#.-),/'$010$#"02()12.)_4'$".2-'/280"'-)=2#"0(N8)21)F0($)2()Q.2()#(-),"''4)

)COMMITTEE B10 ON REACTIVE AND REFRACTORY

METALS AND ALLOYS

A;<;),"#(-#.-),/'$010$#"02()12.),'#&4'88)#(-)G'4-'-)Y(#442L'-)S0"#(07&)#(-)S0"#(07&)!442L)G'4-0(N)U0""0(N8)

)COMMITTEE C01 ON CEMENT

=I+W),"#(-#.-)S'8")K'"%2-)12.)=2&/.'880T'),".'(N"%)21)CL-.#740$)='&'(")K2."#.8)]Y80(N)*D0(a)2.)b?+D&&c)=7>'),/'$0&'(8^)

=I?+),"#(-#.-),/'$010$#"02()12.)92."4#(-)='&'(")

=IWI),"#(-#.-)S'8")K'"%2-8)12.)S0&')21),'""0(N)21)CL-.#740$)='&'(")>L):0$#")M''-4')

=?W?),"#(-#.-),/'$010$#"02()12.)A4'(-'-)CL-.#740$)='&'("8)

)COMMITTEE C09 ON CONCRETE AND

CONCRETE AGGREGATES

=;I),"#(-#.-)9.#$"0$')12.)K#B0(N)#(-)=7.0(N)=2($.'"')S'8"),/'$0&'(8)0()"%')U0'4-)

=;;),"#(-#.-),/'$010$#"02()12.)=2($.'"')!NN.'N#"'8)

=;W),"#(-#.-)S'8")K'"%2-)12.)=2&/.'880T'),".'(N"%)21)=L40(-.0$#4)=2($.'"'),/'$0&'(8)

=J*),"#(-#.-)S'8")K'"%2-)12.)Z>"#0(0(N)#(-)S'8"0(N)E.044'-)=2.'8)#(-),#P'-)A'#&8)21)=2($.'"')

=WJ),"#(-#.-),/'$010$#"02()12.)5'#-LDK0`'-)=2($.'"')


!""#$%&'(")!))

=I*R),"#(-#.-)S'8")K'"%2-)12.)E'(80"L@)5'4#"0T')E'(80"L)],/'$010$)3.#T0"L^@)#(-)!>82./"02()21)=2#.8')!NN.'N#"')

=I*H),"#(-#.-)S'8")K'"%2-)12.)E'(80"L@)5'4#"0T')E'(80"L)],/'$010$)3.#T0"L^@)#(-)!>82./"02()21)U0(')!NN.'N#"')

=IR*),"#(-#.-)9.#$"0$')12.),#&/40(N)U.'8%4L)K0`'-)=2($.'"')

=IW*),"#(-#.-)9.#$"0$')12.)K#B0(N)#(-)=7.0(N)=2($.'"')S'8"),/'$0&'(8)0()"%')O#>2.#"2.L)

=**R),"#(-#.-)S'8")K'"%2-)12.)92"'("0#4)!4B#40)5'#$"0T0"L)21)='&'("D!NN.'N#"')=2&>0(#"02(8)]K2."#.DA#.)K'"%2-^)

=*<+),"#(-#.-),/'$010$#"02()12.)!0.D_(".#0(0(N)!-&0`"7.'8)12.)=2($.'"')

=*WJ),"#(-#.-)E'8$.0/"0T')M2&'($4#"7.')12.)=2(8"0"7'("8)21)=2($.'"')!NN.'N#"'8)

=*W?),"#(-#.-)370-')12.)9'".2N.#/%0$)_`#&0(#"02()21)!NN.'N#"'8)12.)=2($.'"')

=JWJ),"#(-#.-),/'$010$#"02()12.)=%'&0$#4)!-&0`"7.'8)12.)=2($.'"')

=JW<),"#(-#.-)S'8")K'"%2-)12.),/40""0(N)S'(804'),".'(N"%)21)=L40(-.0$#4)=2($.'"'),/'$0&'(8)

=?I*),"#(-#.-)S'8")K'"%2-)12.)=.''/)21)=2($.'"')0()=2&/.'8802()

=?;?),"#(-#.-)S'8")K'"%2-)12.)5'808"#($')"2)E'N.#-#"02()21)O#.N'D,0V')=2#.8')!NN.'N#"')>L)!>.#802()#(-)Q&/#$")0()"%')O28)!(N'4'8)K#$%0(')

=?WR),"#(-#.-)S'8")K'"%2-)12.)9748'):'42$0"L)"%.27N%)=2($.'"')

=<;R),"#(-#.-),/'$010$#"02()12.)!NN.'N#"'8)12.)5#-0#"02(D,%0'4-0(N)=2($.'"')

=<H?),"#(-#.-),/'$010$#"02()12.)=2($.'"')K#-')>L):247&'".0$)A#"$%0(N)#(-)=2("0(7278)K0`0(N)

=I+IR),"#(-#.-),/'$010$#"02()12.)=%'&0$#4)!-&0`"7.'8)12.)Y8')0()9.2-7$0(N)U42P0(N)=2($.'"')

)COMMITTEE C11 ON GYPSUM AND RELATED

BUILDING MATERIALS AND SYSTEMS

=II),"#(-#.-)S'.&0(242NL)5'4#"0(N)"2)3L/87&)#(-)5'4#"'-)A704-0(N)K#"'.0#48)#(-),L8"'&8)


!""#$%&'(")!))

)COMMITTEE C12 ON MORTARS AND GROUTS FOR

UNIT MASONRY

=IJJ),"#(-#.-),/'$010$#"02()12.)!NN.'N#"')12.)K#82(.L)K2."#.)

))

COMMITTEE C16 ON THERMAL INSULATION

=<W*),"#(-#.-)S'8")K'"%2-)12.)_T#47#"0(N)"%')Q(147'($')21)S%'.&#4)Q(874#"02(8)2()_`"'.(#4),".'88)=2..2802()=.#$B0(N)S'(-'($L)21)!78"'(0"0$),"#0(4'88),"''4)

=I*W+),"#(-#.-),/'$010$#"02()12.)U4'`0>4')U0>.278)34#88)A4#(B'")Q(874#"02()Y8'-)"2)_`"'.(#44L)Q(874#"')C:!=)E7$"8)

))

COMMITTEE C26 ON NUCLEAR FUEL CYCLE

=<W<),"#(-#.-)S'8")K'"%2-8)12.)=%'&0$#4@)K#88),/'$".2&'".0$@)#(-),/'$".2$%'&0$#4)!(#4L808)21)M7$4'#.D3.#-')Y.#(07&)E02`0-')92P-'.8)#(-)9'44'"8)

=RR<),"#(-#.-),/'$010$#"02()12.),0("'.'-)Y.#(07&)E02`0-')9'44'"8)

=RWW),"#(-#.-)S'8")K'"%2-8)12.)=%'&0$#4@)K#88),/'$".2&'".0$@),/'$".2$%'&0$#4@)M7$4'#.@)#(-)5#-02$%'&0$#4)!(#4L808)21)M7$4'#.D3.#-')Y.#(L4)M0".#"'),247"02(8))

=H?W),"#(-#.-)S'.&0(242NL)5'4#"0(N)"2)M7$4'#.)K#"'.0#48)

=WH<),"#(-#.-)370-')12.)E'T'42/0(N)S.#0(0(N)9.2N.#&8)0()"%')M7$4'#.)U7'4)=L$4')

=WW*),"#(-#.-),/'$010$#"02()12.)A2.2(DA#8'-)M'7".2()!>82.>0(N)K#"'.0#4),L8"'&8)12.)Y8')0()M7$4'#.),/'(")U7'4),"2.#N')5#$B8)

=IIRJ),"#(-#.-)9.#$"0$')12.)9.'-0$"02()21)"%')O2(NDS'.&)A'%#T02.)21)K#"'.0#48@)Q($47-0(N)G#8"')U2.&8@)Y8'-)0()_(N0(''.'-)A#..0'.),L8"'&8)]_A,^)12.)3'242N0$#4)E08/28#4)21)C0N%DO'T'4)5#-02#$"0T')G#8"')

=I?<*),"#(-#.-)370-')12.)_T#47#"02()21)K#"'.0#48)Y8'-)0()_`"'(-'-),'.T0$')21)Q("'.0&),/'(")M7$4'#.)U7'4)E.L),"2.#N'),L8"'&8)

=I<RI),"#(-#.-)9.#$"0$')12.)[7#4010$#"02()#(-)!$$'/"#($')21)A2.2()A#8'-)K'"#440$)M'7".2()!>82.>'.8)12.)M7$4'#.)=.0"0$#40"L)=2(".24)12.)E.L)=#8B),"2.#N'),L8"'&8)#(-)S.#(8/2."#"02()9#$B#N0(N)


!""#$%&'(")!))

))COMMITTEE D01 ON PAINT AND RELATED COATINGS,

MATERIALS, AND APPLICATIONS

EJ?JI),"#(-#.-)S'8")K'"%2-)12.)9744DZ11),".'(N"%)21)=2#"0(N8)Y80(N)92."#>4')!-%'802()S'8"'.8)

E<<RR),"#(-#.-)S'8")K'"%2-)12.)_T#47#"0(N)!-%'802()>L)d(01'))

ER*;J),"#(-#.-)S'8")K'"%2-)12.)9744DZ11)!-%'802(),".'(N"%)21)=2#"0(N8)2()=2($.'"')Y80(N)92."#>4')9744DZ11)!-%'802()S'8"'.8)

))

COMMITTEE D02 ON PETROLEUM PRODUCTS AND LUBRICANTS

EW?),"#(-#.-)S'8")K'"%2-)12.)G#"'.)0()9'".24'7&)9.2-7$"8)#(-)A0"7&0(278)K#"'.0#48)>L)E08"044#"02()

E*R+)K'"%2-8)21),#&/40(N)9'".24'7&)#(-)9'".24'7&)9.2-7$"8)

EWRJ),"#(-#.-)S'8")K'"%2-)12.)!$0-)#(-)A#8')M7&>'.)>L)=242.DQ(-0$#"2.)S0".#"02()

EWR?),"#(-#.-),/'$010$#"02()12.)E0'8'4)U7'4)Z048)

EI*WH),"#(-#.-)S'8")K'"%2-)12.)E'(80"L@)5'4#"0T')E'(80"L)],/'$010$)3.#T0"L^@)2.)!9Q)3.#T0"L)21)=.7-')9'".24'7&)#(-)O0670-)9'".24'7&)9.2-7$"8)>L)CL-.2&'"'.)K'"%2-)

EI??*),"#(-#.-)S'8")K'"%2-)12.),7417.)0()9'".24'7&)9.2-7$"8)]C0N%DS'&/'.#"7.')K'"%2-^)

EIRW<),"#(-#.-)S'8")K'"%2-)12.)G#"'.)#(-),'-0&'(")0()U7'4)Z048)>L)"%')='(".017N')K'"%2-)]O#>2.#"2.L)9.2$'-7.'^)

E**R<),"#(-#.-)S'8")K'"%2-)12.)9#."0$74#"')=2("#&0(#(")0()!T0#"02()U7'4)>L)O0('),#&/40(N)

E*<**),"#(-#.-)S'8")K'"%2-)12.),7417.)0()9'".24'7&)9.2-7$"8)>L)G#T'4'(N"%)E08/'.80T')eD.#L)U472.'8$'($'),/'$".2&'".L)

E*R+W),"#(-#.-)S'8")K'"%2-)12.)G#"'.)#(-),'-0&'(")0()K0--4')E08"044#"')U7'48)>L)='(".017N')


!""#$%&'(")!))

EJ+?R),"#(-#.-)9.#$"0$')12.)K#(7#4),#&/40(N)21)9'".24'7&)#(-)9'".24'7&)9.2-7$"8)

EJIR<),"#(-#.-)S'8")K'"%2-)12.)U.'')G#"'.)#(-)9#."0$74#"')=2("#&0(#"02()0()E08"044#"')U7'48)]:087#4)Q(8/'$"02()9.2$'-7.'8^)

EJ*WJ),"#(-#.-)S'8")K'"%2-)12.),7417.)0()9'".24'7&)#(-)9'".24'7&)9.2-7$"8)>L)_('.NL)E08/'.80T')eD.#L)U472.'8$'($'),/'$".2&'".L)

E?J?*),"#(-#.-)S'8")K'"%2-)12.)9#."0$74#"')=2("#&0(#"02()0()!T0#"02()U7'48)>L)O#>2.#"2.L)U04".#"02()

E<*IR),"#(-#.-)S'8")K'"%2-)12.)9#."0$74#"')=2("#&0(#"02()0()K0--4')E08"044#"')U7'48)>L)O#>2.#"2.L)U04".#"02()

E<**J),"#(-#.-)9.#$"0$')12.)Q(D,'.T0$')K2(0"2.0(N)21)O7>.0$#"0(N)Z04)12.)!7`040#.L)92P'.)94#(")_670/&'(")

))COMMITTEE D04 ON ROAD AND PAVING MATERIALS

EJJH),"#(-#.-)=4#88010$#"02()12.),0V'8)21)!NN.'N#"')12.)52#-)#(-)A.0-N')=2(8".7$"02()

))

COMMITTEE D05 ON COAL AND COKE E;*H<),"#(-#.-)S'8")K'"%2-)12.)3.288)=#42.010$):#47')21)=2#4)#(-)=2B')>L)"%')Q82/'.0>24)A2&>)=#42.0&'"'.))))COMMITTEE D09 ON ELECTRICAL AND ELECTRONIC

INSULATING MATERIALS

E***+),"#(-#.-),/'$010$#"02()12.)924L]:0(L4)=%42.0-'^)Q(874#"02()12.)G0.')#(-)=#>4'@)R?f=)Z/'.#"02()

))

COMMITTEE D10 ON PACKAGING

E*H<+),"#(-#.-)S'8")K'"%2-)12.)!-%'802()21)9.'887.'D,'(80"0T')S#/')"2)U0>'.>2#.-)#")W+)!(N4')#(-)=2(8"#("),".'88)

)


!""#$%&'(")!))

)COMMITTEE D13 ON TEXTILES

E?JHW),"#(-#.-)370-')12.)=#.'),L&>248)12.)=#.')Q(8".7$"02(8)2()S'`"04')9.2-7$"8)

))

COMMITTEE D18 ON SOIL AND ROCK

EJ*I),"#(-#.-)9.#$"0$')12.)E.L)9.'/#.#"02()21),204),#&/4'8)12.)9#."0$4'D,0V')!(#4L808)#(-)E'"'.&0(#"02()21),204)=2(8"#("8)

EJ**),"#(-#.-)S'8")K'"%2-)12.)9#."0$4'D,0V')!(#4L808)21),2048)

EJ*?),"#(-#.-)S'8")K'"%2-)12.)='(".017N')K208"7.')_670T#4'(")21),2048)

)EJ*R)S'8")K'"%2-)12.),%.0(B#N')U#$"2.8)21),2048)>L)"%')K'.$7.L)K'"%2-)

E<WH),"#(-#.-)S'8")K'"%2-8)12.)O#>2.#"2.L)=2&/#$"02()=%#.#$"'.08"0$8)21),204)Y80(N),"#(-#.-)_112.")]I* J++)1"D4>1g1"; ]<++)BMD&g&;^^)

EH?J),"#(-#.-)S'8")K'"%2-8)12.),/'$010$)3.#T0"L)21),204),240-8)>L)G#"'.)9L$(2&'"'.)

EIIJ+),"#(-#.-)S'8")K'"%2-8)12.)!&27(")21)K#"'.0#4)0(),2048)U0('.)"%#()M2a)*++)]R?D&^),0'T')

EI??R),"#(-#.-)S'8")K'"%2-8)12.)O#>2.#"2.L)=2&/#$"02()=%#.#$"'.08"0$8)21),204)Y80(N)K2-010'-)_112.")]?<@+++)1"D4>1g1";)]*@R++)BMD&g&;^^)

EI??H),"#(-#.-)S'8")K'"%2-)12.)K208"7.')=2("'(")9'('".#"02()5'808"#($')5'4#"02(8%0/8)21)U0('D3.#0('-),2048)

E*I<<),"#(-#.-)S'8")K'"%2-)12.)Y($2(10('-)=2&/.'880T'),".'(N"%)21)=2%'80T'),204)

E**I<),"#(-#.-)S'8")K'"%2-8)12.)O#>2.#"2.L)E'"'.&0(#"02()21)G#"'.)]K208"7.'^)=2("'(")21),204)#(-)52$B)>L)K#88)

E**IR),"#(-#.-)9.#$"0$')12.)G'")9.'/#.#"02()21),204),#&/4'8)12.)9#."0$4'D,0V')!(#4L808)#(-)E'"'.&0(#"02()21),204)=2(8"#("8)

E*J;J),"#(-#.-)S'8")K'"%2-)12.)9'.&'#>040"L)21)3.#(74#.),2048)]=2(8"#(")C'#-^)

E*J;?),"#(-#.-)S'8")K'"%2-8)12.)Z('DE0&'(802(#4)=2(8240-#"02()9.2/'."0'8)21),2048)Y80(N)Q($.'&'("#4)O2#-0(N)


!""#$%&'(")!))

E*JHR),"#(-#.-)9.#$"0$')12.)=4#88010$#"02()21),2048)12.)_(N0(''.0(N)97./28'8)]Y(010'-),204)=4#88010$#"02(),L8"'&^)

E*JHH),"#(-#.-)9.#$"0$')12.)E'8$.0/"02()#(-)Q-'("010$#"02()21),2048)]:087#4DK#(7#4)9.2$'-7.'^)

E*<<J),"#(-#.-)S'8")K'"%2-)12.)S.0#`0#4)=2&/.'880T'),".'(N"%)21)Y(-.#0('-)52$B)=2.'),/'$0&'(8)G0"%27")92.')9.'887.')K'#87.'&'("8)

E*HJ?),"#(-#.-)S'8")K'"%2-)12.)O#>2.#"2.L)E'"'.&0(#"02()21)9748'):'42$0"0'8)#(-)Y4".#82(0$)_4#8"0$)=2(8"#("8)21)52$B)

E*H?+),"#(-#.-)S'8")K'"%2-)12.)Y($2(8240-#"'-DY(-.#0('-)S.0#`0#4)=2&/.'8802()S'8")2()=2%'80T'),2048)

E*W;<),"#(-#.-)S'8")K'"%2-)12.)E0.'$")S'(804'),".'(N"%)21)Q("#$")52$B)=2.'),/'$0&'(8)

E*W;H),"#(-#.-)S'8")K'"%2-)12.)Y($2(10('-)=2&/.'880T'),".'(N"%)21)Q("#$")52$B)=2.'),/'$0&'(8)

E*WRJ),"#(-#.-)S'8")K'"%2-8)12.)K208"7.'@)!8%@)#(-)Z.N#(0$)K#""'.)21)9'#")#(-)Z"%'.)Z.N#(0$),2048)

E;+H+),"#(-#.-)S'8")K'"%2-)12.)E0.'$"),%'#.)S'8")21),2048)7(-'.)=2(8240-#"'-)E.#0('-)=2(-0"02(8)

E;IJH),"#(-#.-)S'8")K'"%2-)12.)_4#8"0$)K2-740)21)Q("#$")52$B)=2.'),/'$0&'(8)0()Y(0#`0#4)=2&/.'8802()

E;RJ+),"#(-#.-)9.#$"0$')12.)K0(0&7&)5'670.'&'("8)12.)!N'($0'8)_(N#N'-)0()S'8"0(N)#(-g2.)Q(8/'$"02()21),204)#(-)52$B)#8)Y8'-)0()_(N0(''.0(N)E'80N()#(-)=2(8".7$"02()

E;W<R),"#(-#.-)S'8")K'"%2-)12.),/40""0(N)S'(804'),".'(N"%)21)Q("#$")52$B)=2.'),/'$0&'(8)

E;WWW),"#(-#.-)S'8")K'"%2-8)12.)"%')E'"'.&0(#"02()21)"%')K2-7478)#(-)E#&/0(N)9.2/'."0'8)21),2048)Y80(N)"%')=L$40$)S.0#`0#4)!//#.#"78)

EJ+I?),"#(-#.-)S'8")K'"%2-8)12.)K2-7478)#(-)E#&/0(N)21),2048)>L)5'82(#("D=247&()K'"%2-)

EJIH<),"#(-#.-)S'8")K'"%2-)12.)Z('DE0&'(802(#4)=2(8240-#"02()9.2/'."0'8)21),#"7.#"'-)=2%'80T'),2048)Y80(N)=2(".244'-D,".#0()O2#-0(N)

EJ**+),"#(-#.-)9.#$"0$'8)12.)9.'8'.T0(N)#(-)S.#(8/2."0(N),204),#&/4'8)


!""#$%&'(")!))

EJ**I),"#(-#.-)S'8")K'"%2-)12.)E08/'.80T')=%#.#$"'.08"0$8)21)=4#L),204)>L)E27>4')CL-.2&'"'.)

EJ*?;),"#(-#.-)S'8")K'"%2-8)12.)K#`0&7&)Q(-'`)E'(80"L)#(-)Y(0")G'0N%")21),2048)Y80(N)#):0>.#"2.L)S#>4')

EJ*?J),"#(-#.-)S'8")K'"%2-8)12.)K0(0&7&)Q(-'`)E'(80"L)#(-)Y(0")G'0N%")21),2048)#(-)=#4$74#"02()21)5'4#"0T')E'(80"L)

EJ;IH),"#(-#.-)S'8")K'"%2-8)12.)O0670-)O0&0"@)94#8"0$)O0&0"@)#(-)94#8"0$0"L)Q(-'`)21),2048)

EJJ+J),"#(-#.-)S'8")K'"%2-)12.)E'"'.&0(#"02()21)92.'):247&')#(-)92.'):247&')E08".0>7"02()21),204)#(-)52$B)>L)K'.$7.L)Q(".7802()92.280&'".L)

EJJ+?),"#(-#.-)S'8")K'"%2-)12.)=.''/)21)=L40(-.0$#4),21")52$B)=2.'),/'$0&'(8)0()Y(0#`0#4)=2&/.'8802(8)

EJJ?*),"#(-#.-)9.#$"0$')12.)eD5#L)5#-02N.#/%L)21),204),#&/4'8)

EJ?*?),"#(-#.-)S'8")K'"%2-)12.)9'.&'#>040"L)21)52$B8)>L)U42P0(N)!0.)

EJ?J*),"#(-#.-)S'8")K'"%2-)12.)92.')G#"'.)_`".#$"02()#(-)E'"'.&0(#"02()21)"%'),247>4'),#4")=2("'(")21),2048)>L)5'1.#$"2&'"'.)

EJ<I*),"#(-#.-)9.#$"0$')12.)=#4$74#"0(N)S%'.&#4)E011780T0"L)21)52$B8)

EJ<J;),"#(-#.-)S'8")K'"%2-)12.)E'"'.&0(#"02()21)G#"'.)]K208"7.'^)=2("'(")21),204)>L)K0$.2P#T')ZT'()C'#"0(N)

EJ<JJ),"#(-#.-)S'8")K'"%2-)12.),4#B')E7.#>040"L)21),%#4'8)#(-),0&04#.)G'#B)52$B8)

EJ<JR),"#(-#.-)S'8")K'"%2-)12.)Q-'("010$#"02()#(-)=4#88010$#"02()21)E08/'.80T')=4#L),2048)>L)"%')90(%24')S'8")

EJR?;),"#(-#.-)370-')12.)_T#47#"0(N@),'4'$"0(N@)#(-),/'$01L0(N)A#4#($'8)#(-),"#(-#.-)K#88'8)12.)Y8')0(),204@)52$B@)#(-)=2(8".7$"02()K#"'.0#48)S'8"0(N)

EJR<R),"#(-#.-)S'8")K'"%2-)12.)=2(8240-#"'-)Y(-.#0('-)S.0#`0#4)=2&/.'8802()S'8")12.)=2%'80T'),2048)

EJWJ;),"#(-#.-)S'8")K'"%2-)12.),%.0(B#N')U#$"2.8)21),2048)>L)"%')G#`)K'"%2-)

EJW?W),"#(-#.-)S'8")K'"%2-)12.)E'"'.&0(#"02()21)G#"'.)]K208"7.'^)=2("'(")21),204)AL)E0.'$")C'#"0(N)


!""#$%&'(")!))

E?+H+),"#(-#.-)S'8")K'"%2-)12.)5#/0-)E'"'.&0(#"02()21)9'.$'(")=2&/#$"02()

E?+HJ),"#(-#.-)S'8")K'"%2-8)12.)K'#87.'&'(")21)CL-.#740$)=2(-7$"0T0"L)21),#"7.#"'-)92.278)K#"'.0#48)Y80(N)#)U4'`0>4')G#44)9'.&'#&'"'.)

E?+W*),"#(-#.-)9.#$"0$')12.)E'80N()#(-)Q(8"#44#"02()21)3.27(-P#"'.)K2(0"2.0(N)G'448)

E?;II),"#(-#.-)S'8")K'"%2-)12.)O2#-)=2(".244'-)=L$40$)S.0#`0#4),".'(N"%)21),204)

E?J+R),"#(-#.-)S'8")K'"%2-)12.)_4#8"0$)K2-740)21)Y(-.#0('-)Q("#$")52$B)=2.'),/'$0&'(8)0()S.0#`0#4)=2&/.'8802()G0"%27")92.')9.'887.')K'#87.'&'(")

E???+),"#(-#.-)S'8")K'"%2-)12.),/'$010$)3.#T0"L)21),204),240-8)>L)3#8)9L$(2&'"'.)

E?<+R),"#(-#.-)S'8")K'"%2-)12.)9'.12.&0(N)O#>2.#"2.L)E0.'$"),%'#.),".'(N"%)S'8"8)21)52$B),/'$0&'(8)Y(-'.)=2(8"#(")M2.&#4)U2.$')

E?HRH),"#(-#.-)370-'8)12.)Y80(N)52$BDK#88)=4#88010$#"02(),L8"'&8)12.)_(N0(''.0(N)97./28'8)

))

COMMITTEE D19 ON WATER

E?I*),"#(-#.-)S'8")K'"%2-8)12.)=%42.0-')Q2()0()G#"'.)

E?I<),"#(-#.-)S'8")K'"%2-)12.),741#"')Q2()0()G#"'.)

E?W<),"#(-#.-)370-')12.)5'/2."0(N)5'874"8)21)!(#4L808)21)G#"'.)

EII*W),"#(-#.-)S'.&0(242NL)5'4#"0(N)"2)G#"'.)

EIIRW),"#(-#.-)S'8")K'"%2-8)12.)U472.0-')Q2()0()G#"'.)

EI*W;),"#(-#.-)S'8")K'"%2-8)12.)/C)21)G#"'.)

E;;R+),"#(-#.-)9.#$"0$'8)12.),#&/40(N)G#"'.)1.2&)=428'-)=2(-70"8)

E;H<R),"#(-#.-)S'8")K'"%2-8)12.)M0".0"'DM0".#"')0()G#"'.)

ER*H*),"#(-#.-)9.#$"0$')12.),'"D7/@)=#40>.#"02(@)#(-)[7#40"L)=2(".24)21)Q(8".7&'("8)Y8'-)12.)5#-02#$"0T0"L)K'#87.'&'("8)

))

COMMITTEE D20 ON PLASTICS


!""#$%&'(")!))

E?J;),"#(-#.-)9.#$"0$'8)12.)_T#47#"0(N)"%')5'808"#($')21)94#8"0$8)"2)=%'&0$#4)5'#N'("8)

E*WW*),"#(-#.-)9.#$"0$')12.)Z>"#0(0(N)CL-.28"#"0$)2.)9.'887.')E'80N()A#808)12.)hU0>'.N4#88i)]34#88DU0>'.D5'0(12.$'-)S%'.&28'""0(ND5'80(^)90/')#(-)U0""0(N8)

))

COMMITTEE D22 ON AIR QUALITY

E;<H?),"#(-#.-)S'8")K'"%2-8)12.),#&/40(N)#(-)E'"'.&0(#"02()21)9#."0$74#"')K#""'.)0(),"#$B)3#8'8)

))

COMMITTEE D28 ON ACTIVATED CARBON

E;H+;),"#(-#.-)S'8")K'"%2-)12.)M7$4'#.D3.#-')!$"0T#"'-)=#.>2()

))

COMMITTEE D33 ON PROTECTIVE COATING AND LINING WORK FOR POWER GENERATION FACILITIES

E;HJ;),"#(-#.-)9.#$"0$')12.)[7#40"L)!887.#($')12.)9.2"'$"0T')=2#"0(N8)!//40'-)"2)M7$4'#.)U#$040"0'8)

E;WII),"#(-#.-)S'8")K'"%2-)12.)_T#47#"0(N)=2#"0(N8)Y8'-)0()O0N%"DG#"'.)M7$4'#.)92P'.)94#("8)#"),0&74#"'-)E'80N()A#808)!$$0-'(")]EA!^)=2(-0"02(8)

E;WI*),"#(-#.-)S'8")K'"%2-)12.)=%'&0$#4)5'808"#($')21)=2#"0(N8)#(-)O0(0(N8)12.)Y8')0()M7$4'#.)92P'.)94#("8)

EJ+H*),"#(-#.-)S'8")K'"%2-)12.)_11'$"8)21)3#&&#)5#-0#"02()2()=2#"0(N8)12.)Y8')0()M7$4'#.)92P'.)94#("8)

EJ**R),"#(-#.-)9.#$"0$')12.)[7#4010$#"02()21)=2#"0(N)!//40$#"2.8)12.)!//40$#"02()21)=2#"0(N8)"2)=2($.'"'),7.1#$'8)

EJ**H),"#(-#.-)9.#$"0$')12.)[7#4010$#"02()21)=2#"0(N)!//40$#"2.8)12.)!//40$#"02()21)=2#"0(N8)"2),"''4),7.1#$'8)

EJ*H<),"#(-#.-)9.#$"0$')12.)E'"'.&0(0(N)=2#"0(N)=2(".#$"2.)[7#4010$#"02(8)12.)M7$4'#.)92P'.'-)_4'$".0$)3'('.#"02()U#$040"0'8)

!""#$%&'(")!))

E?+H+),"#(-#.-)S'8")K'"%2-)12.)5#/0-)E'"'.&0(#"02()21)9'.$'(")=2&/#$"02()

E?+HJ),"#(-#.-)S'8")K'"%2-8)12.)K'#87.'&'(")21)CL-.#740$)=2(-7$"0T0"L)21),#"7.#"'-)92.278)K#"'.0#48)Y80(N)#)U4'`0>4')G#44)9'.&'#&'"'.)

E?+W*),"#(-#.-)9.#$"0$')12.)E'80N()#(-)Q(8"#44#"02()21)3.27(-P#"'.)K2(0"2.0(N)G'448)

E?;II),"#(-#.-)S'8")K'"%2-)12.)O2#-)=2(".244'-)=L$40$)S.0#`0#4),".'(N"%)21),204)

E?J+R),"#(-#.-)S'8")K'"%2-)12.)_4#8"0$)K2-740)21)Y(-.#0('-)Q("#$")52$B)=2.'),/'$0&'(8)0()S.0#`0#4)=2&/.'8802()G0"%27")92.')9.'887.')K'#87.'&'(")

E???+),"#(-#.-)S'8")K'"%2-)12.),/'$010$)3.#T0"L)21),204),240-8)>L)3#8)9L$(2&'"'.)

E?<+R),"#(-#.-)S'8")K'"%2-)12.)9'.12.&0(N)O#>2.#"2.L)E0.'$"),%'#.),".'(N"%)S'8"8)21)52$B),/'$0&'(8)Y(-'.)=2(8"#(")M2.&#4)U2.$')

E?HRH),"#(-#.-)370-'8)12.)Y80(N)52$BDK#88)=4#88010$#"02(),L8"'&8)12.)_(N0(''.0(N)97./28'8)

))

COMMITTEE D19 ON WATER

E?I*),"#(-#.-)S'8")K'"%2-8)12.)=%42.0-')Q2()0()G#"'.)

E?I<),"#(-#.-)S'8")K'"%2-)12.),741#"')Q2()0()G#"'.)

E?W<),"#(-#.-)370-')12.)5'/2."0(N)5'874"8)21)!(#4L808)21)G#"'.)

EII*W),"#(-#.-)S'.&0(242NL)5'4#"0(N)"2)G#"'.)

EIIRW),"#(-#.-)S'8")K'"%2-8)12.)U472.0-')Q2()0()G#"'.)

EI*W;),"#(-#.-)S'8")K'"%2-8)12.)/C)21)G#"'.)

E;;R+),"#(-#.-)9.#$"0$'8)12.),#&/40(N)G#"'.)1.2&)=428'-)=2(-70"8)

E;H<R),"#(-#.-)S'8")K'"%2-8)12.)M0".0"'DM0".#"')0()G#"'.)

ER*H*),"#(-#.-)9.#$"0$')12.),'"D7/@)=#40>.#"02(@)#(-)[7#40"L)=2(".24)21)Q(8".7&'("8)Y8'-)12.)5#-02#$"0T0"L)K'#87.'&'("8)

))

COMMITTEE D20 ON PLASTICS

Attachment A


!""#$%&'(")!))

EJ?;R),"#(-#.-)370-')12.)_8"#>408%0(N)9.2$'-7.'8)"2)[7#401L)#(-)='."01L)9'.82(('4)9'.12.&0(N)=2#"0(N)#(-)O0(0(N)G2.B)Q(8/'$"02()0()M7$4'#.)U#$040"0'8))

EJ?;H),"#(-#.-)S'.&0(242NL)5'4#"0(N)"2)9.2"'$"0T')=2#"0(N)#(-)O0(0(N)G2.B)12.)92P'.)3'('.#"02()U#$040"0'8)

E?I;W),"#(-#.-),/'$010$#"02()12.),#&/4')9.'/#.#"02()12.)[7#4010$#"02()S'8"0(N)21)=2#"0(N8)"2)>')Y8'-)0()M7$4'#.)92P'.)94#("8)

E?IJJ),"#(-#.-)370-')12.)Y8')21)9.2"'$"0T')=2#"0(N),"#(-#.-8)0()M7$4'#.)92P'.)94#("8)

E?I<;),"#(-#.-)370-')12.)_8"#>408%0(N)#)9.2N.#&)12.)=2(-0"02()!88'88&'(")21)=2#"0(N),'.T0$')O'T'4)Q)=2#"0(N),L8"'&8)0()M7$4'#.)92P'.)94#("8)

ERI+H),"#(-#.-)370-')12.)_8"#>408%0(N)[7#4010$#"02(8)12.)#)M7$4'#.)=2#"0(N8),/'$0#408")

ERI<R),"#(-#.-)370-')12.)_8"#>408%0(N)9.2$'-7.'8)"2)K2(0"2.)"%')9'.12.&#($')21),#1'"LD5'4#"'-)=2#"0(N),'.T0$')O'T'4)QQQ)O0(0(N),L8"'&8)0()#()Z/'.#"0(N)M7$4'#.)92P'.)94#(")

ERJWI),"#(-#.-)370-')12.)K#(#N'&'(")21)M2(D=2(12.&0(N)=2#"0(N8)0()=2#"0(N),'.T0$')O'T'4)Q)!.'#8)21)M7$4'#.)92P'.)94#("8)

))

COMMITTEE E01 ON ANALYTICAL CHEMISTRY FOR METALS, ORES, AND RELATED MATERIALS

_<+),"#(-#.-)9.#$"0$')12.)!(#4L808)21)K'"#48@)Z.'8@)#(-)5'4#"'-)K#"'.0#48)>L),/'$".2/%2"2&'".L)

_I*+),"#(-#.-)S'8")K'"%2-8)12.)=%'&0$#4)!(#4L808)21)S0"#(07&)#(-)S0"#(07&)!442L8))))

COMMITTEE E05 ON FIRE STANDARDS

_HJ),"#(-#.-)S'8")K'"%2-)12.),7.1#$')A7.(0(N)=%#.#$"'.08"0$8)21)A704-0(N)K#"'.0#48))

_HIJ),"#(-#.-)S'8")K'"%2-)12.)U0.')S'8"8)21)9'('".#"02()U0.'8"2/),L8"'&8)

_IIW),"#(-#.-)S'8")K'"%2-8)12.)U0.')S'8"8)21)A704-0(N)=2(8".7$"02()#(-)K#"'.0#48)

_*H?W),"#(-#.-)370-')12.),0V')K'#87.'&'(")21)M#(2/#."0$4'8)Y80(N)!"2&0$)U2.$')K0$.28$2/L)


!""#$%&'(")!))

))

COMMITTEE E06 ON PERFORMACE OF BUILDINGS

_JHH),"#(-#.-)S'8")K'"%2-8)12.),".'(N"%)21)!($%2.8)0()=2($.'"')_4'&'("8)

_RJI),"#(-#.-)S'8")K'"%2-)12.)E'"'.&0(0(N)!0.)=%#(N')0()#),0(N4')F2(')>L)K'#(8)21)#)S.#$'.)3#8)E047"02()

))

COMMITTEE E08 ON FATIGUE AND FRACTURE

_;WW),"#(-#.-)S'8")K'"%2-)12.)O0('#.D_4#8"0$)94#('D,".#0()U.#$"7.')S27N%('88)Q$)21)K'"#440$)K#"'.0#48)

_II?*)S'8")K'"%2-)12.)E'"'.&0(0(N)jD5)=7.T'8)

_IH*+),"#(-#.-)S'8")K'"%2-)12.)K'#87.'&'(")21)U.#$"7.')S27N%('88)

))

COMMITTEE E10 ON NUCLEAR TECHNOLOGY AND APPLICATIONS

_IHI),"#(-#.-)S'8")K'"%2-8)12.)E'"'$"2.)=#40>.#"02()#(-)!(#4L808)21)5#-02(7$40-'8)

_IH?),"#(-#.-)9.#$"0$')12.)E'80N()21),7.T'044#($')9.2N.#&8)12.)O0N%"DG#"'.)K2-'.#"'-)M7$4'#.)92P'.)5'#$"2.):'88'48)

_*<I),"#(-#.-)9.#$"0$')12.)E'"'.&0(0(N)M'7".2()U47'($'@)U47'($')5#"'@)#(-),/'$".#)>L)5#-02#$"0T#"02()S'$%(067'8)

_*<;),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)U#8"DM'7".2()5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)Q.2()

_*<J),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)U#8"DM'7".2()5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)M0$B'4)

_JH*),"#(-#.-)370-')12.)!//40$#"02()21)M'7".2()S.#(8/2.")K'"%2-8)12.)5'#$"2.):'88'4),7.T'044#($'@)_R+<)]QQE^)

_?+W),"#(-#.-)370-')12.)Q(D,'.T0$')!(('#40(N)21)O0N%"DG#"'.)K2-'.#"'-)M7$4'#.)5'#$"2.):'88'48)


!""#$%&'(")!))

_?*;),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)U#8"DM'7".2()5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)=2//'.)

_?*<),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)U#8"DM'7".2()5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)S0"#(07&)

_<W;),"#(-#.-)9.#$"0$')12.)=%#.#$"'.0V0(N)M'7".2()_`/287.'8)0()Q.2()#(-)O2P)!442L),"''48)0()S'.&8)21)E08/4#$'&'("8)9'.)!"2&)]E9!^@)_ R+<]QE^))

_R+J),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)Y.#(07&D*;H)

_R+?),"#(-#.-)S'8")K'"%2-)12.)K'#87.0(N)5'#$"02()5#"'8)>L)5#-02#$"0T#"02()21)M'/"7(07&D*;R)

_HJJ),"#(-#.-)370-')12.),'(82.),'")E'80N()#(-)Q..#-0#"02()12.)5'#$"2.),7.T'044#($'@)_)R+<]QQ=^)

_H?J),"#(-#.-)S'8")K'"%2-)12.)!//40$#"02()#(-)!(#4L808)21),240-),"#"')S.#$B)5'$2.-'.)],,S5^)K2(0"2.8)12.)5'#$"2.),7.T'044#($'@)_R+<)]QQQA^)

_WI+),"#(-#.-)S'8")K'"%2-)12.)!//40$#"02()#(-)!(#4L808)21)C'407&)!$$7&74#"02()U47'($')K2(0"2.8)12.)5'#$"2.):'88'4),7.T'044#($'@)_R+<)]QQQ=^)

_WJJ),"#(-#.-)370-')12.)!//40$#"02()21)M'7".2(),/'$".7&)!-k78"&'(")K'"%2-8)0()5'#$"2.),7.T'044#($'@)_R+<)]QQ!^)

_I++?),"#(-#.-)S'8")K'"%2-)12.)!//40$#"02()#(-)!(#4L808)21)5#-02&'".0$)K2(0"2.8)12.)5'#$"2.):'88'4),7.T'044#($'@)_)R+<]QQQ!^)

_I+IH),"#(-#.-)370-')12.)!//40$#"02()21)!,SK)_T#47#"'-)=.288),'$"02()E#"#)U04'@)K#".0`)_)R+<)]QQA^)

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COMMITTEE E11 ON QUALITY AND STATISTICS

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COMMITTEE E28 ON MECHANICAL TESTING

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COMMITTEE F12 ON SECURITY SYSTEMS AND EQUIPMENT

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COMMITTEE F16 ON FASTENERS

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COMMITTEE F17 ON PLASTIC PIPING SYSTEMS

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COMMITTEE F25 ON SHIPS AND MARINE TECHNOLOGY

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)


Attachment B

PRIORITY LIST OF STANDARDS IN NEED OF BALLOTING

Committee A01 on Steel, Stainless Steel and Related Alloys A185 Standard Specification for Steel Welded Wire Reinforcement, Plain, for Concrete A496 Standard Specification for Steel Wire, Deformed, for Concrete Reinforcement A497 Standard Specification for Steel Welded Wire Reinforcement, Deformed, for Concrete A501 Standard Specification for Hot Formed Welded and Seamless Carbon Steel Structural Tubing A537 Standard Specification for Pressure Vessel Plates, Heat Treated, Carbon Manganese Silicon Steel

Committee B05 on Copper and Copper Alloys B61 Standard Specification for Steam or Valve Bronze Castings

Committee C26 on Nuclear Fuel Cycle C1174 Standard Practice for Prediction of the Long Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High Level Radioactive Waste C1671 Standard Practice for Qualification and Acceptance of Boron Based Metallic Neutron Absorbers for Nuclear Criticality Control for Dry Cask Storage Systems and Transportation Packaging

Committee C01 on Cement C191 Standard Test Methods for Time of Setting of Hydraulic Cement by Vicat Needle

Committee D02 on Petroleum Products and Lubricants D1552 Standard Test Method for Sulfur in Petroleum Products (High Temperature Method) D2276 Standard Test Method for Particulate Contaminant in Aviation Fuel by Line Sampling

Committee D18 on Soil and Rock D421 Standard Practice for Dry Preparation of Soil Samples for Particle Size Analysis and Determination of Soil Constants D422 Standard Test Method for Particle Size Analysis of Soils D425 Standard Test Method for Centrifuge Moisture Equivalent of Soils D4525 Standard Test Method for Permeability of Rocks by Flowing Air D4612 Standard Practice for Calculating Thermal Diffusivity of Rocks D4943 Standard Test Method for Shrinkage Factors of Soils by the Wax Method


Attachment B

D5080 Standard Test Method for Rapid Determination of Percent Compaction D5607 Standard Test Method for Performing Laboratory Direct Shear Strength Tests of Rock Specimens Under Constant Normal Force D5878 Standard Guides for Using Rock Mass Classification Systems for Engineering Purposes

Committee D18 on Water D7282 Standard Practice for Set up, Calibration, and Quality Control of Instruments Used for Radioactivity Measurements

Committee D33 on Protective Coating and Lining Work for Power Generation Facilities

D3843 Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities D3911 Standard Test Method for Evaluating Coatings Used in Light Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions D4286 Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities D5144 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants D5163 Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants D7491 Standard Guide for Management of Non Conforming Coatings in Coating Service Level I Areas of Nuclear Power Plants

Committee E10 on Nuclear Technology and Applications E1167 Standard Guide for Radiation Protection Program for Decommissioning Operations E1168 Standard Guide for Radiological Protection Training for Nuclear Facility Workers E29 Standard Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications

Committee E11 on Quality and Statistics E29 Standard Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications

Committee E28 on Mechanical Testing E604 Standard Test Method for Dynamic Tear Testing of Metallic Materials


ACTION PLANS FOR NUCLEAR INDUSTRY

Incorporation of revised ASTM E185 and E2215 into 10 CFR 50 Appendix H

At the ASTM E10.02 Subcommittee meeting on January 30-31, 2012, there were discussions on revising ASTM E185 and E2215 to better reflect open items with respect to proposed changes to the corresponding NRC regulation, 10 CFR 50 Appendix H. For E185, the principal changes were with respect to the design of reactor vessel surveillance programs for new plants. For E2215, the principal changes were with respect to the design of reactor vessel surveillance programs for operating plants. The modifications to the new standards will be circulated to ASTM E10.02 Subcommittee members for review and comment prior to balloting. Once the comments have been processed, the two revised standards will be balloted for approval by the subcommittee.

The modifications will also be circulated to individuals within the NRC New Plants and License Renewal organizations for review and subsequent discussion. The objective is to ensure all relevant open issues have been addressed concerning the design of surveillance programs for new plants and for the modifications to surveillance programs for operating plants to support license renewal (extended operating periods). The goal is to make the revisions to ASTM E185 and E2215 relevant so that the revised standards can be incorporated directly into 10 CFR 50 Appendix H with minimal additional effort by the NRC. As soon as practical, nuclear industry representatives will initiate a Request for Rulemaking (most likely through the PWR Owners Group and the Materials Reliability Project via an appropriate interface organization such as NEI). Nuclear industry representatives will then support the request as needed. Rulemaking is a two-year process once it has been approved to begin; therefore, the key to success is performing the interfacing with the NRC New Plants and License Renewal groups to ascertain both the need for updating the NRC Regulation and the scope of changes to ASTM E185 and E2215 that will be drawn into the Appendix H revision.


Coordination of ASTM Committee C26 on Nuclear Fuel Cycle with ANS on use of standards

ANS provided ASTM a list of their standards. As a result, ASTM Committee C26 (including Subcommittees C26.02, C26.03, C26.05, C26.10, and C26.12) has been requested to review and compare the ANS list for overlap and gaps. Committee C26 was also tasked to determine how the handling of nuclear waste is addressed in NRC regulations. Subcommittee E10.05 was asked to perform a similar review against its standards. The purpose of the review is to clarify if overlap exists between both SDOs’ standards, and, if so, to review for applicability and state-of-the-art content. Each group was also asked to determine if any existing ASTM standards should be used as a reference in NRC regulations and guidance, in addition to any gaps in technology that should be included in an ASTM standard that might improve the value of NRC regulations or guidance. Once this screening effort has been completed and the results processed, the information will be discussed with ANS with respect to the next course of action.


Documents

ASTM International Roadmap in Support of Commercial ... By the late 1990s there was a broad-based initiative underway in the commercial nuclear power industry to resolve longstanding