This database provides information on standards that have been incorporated by reference into the US Code of Federal Regulations (CFR). To obtain copies of the standards referenced, information should be provided in the referenced CFR section about how to obtain a copy. Alternatively, individuals can check with the standards publisher, a standards resellers or for a limited number of standards used in regulations, consult the American National Standards Institute (ANSI) Incorporated by Reference (IBR) Portal. This portal provides a mechanism for limited and free access to some of the standards that have been incorporated by reference in the U.S. Code of Federal Regulations (CFR).
Incorporated by (Agency) Sort descending | FR Citation | CFR Citation | Document Number | Document Edition / Year | Title of Standard | Standard Publishing Organization |
---|---|---|---|---|---|---|
Nuclear Regulatory Commission | 87 FR 65128 | 10 CFR 50 | ASME NQA-1-2012 | 2012 | American Society of Mechanical Engineers 2019-2020 Code Editions | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(1) | ASME B&PV Code | 1980 | Boiler and Pressure Vessel Code, Section III, Division 1 | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xix) | ASME B&PV Code | 1997 | Boiler and Pressure Vessel Code, Section XI, 1997 Addenda of IWA-2240, 1998 Edition through the latest edition and addenda, IWA-4520(c), 1997 Addenda through the latest edition and addenda | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(g)(4)(ii) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 73 App. B, I B b 2 a | ISO 389 | 1975 | Standard Reference Zero for the Calibration of Puretone Audiometer | International Organization for Standardization | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(4) | NRC Regulatory Guide 1.84 | 2010 | Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 35 | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 10 CFR 73.26(l)(1) | ISO 1496 | 1978 | General Cargo Containers | International Organization for Standardization | |
Nuclear Regulatory Commission | 87 FR 11934 | 10 CFR 50 | ASME BPVC XI-1, Revision 20 | 2019 | Approval of American Society of Mechanical Engineers' Code Cases | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.55a(d)(2) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section III, paragraph NCA-1140, Subsection NCA | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(i) | ASME B&PV Code | 1992 | Boiler and Pressure Vessel Code, Section III, 1992 Edition with the 1992 Addenda of Section II | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 89 FR 70449 | 10 CFR 50 | ASME OM 2022 | 2022 | American Society of Mechanical Engineers 2021-2022 Code Editions | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 34.20(a)(1) | ANSI N432 | 1980 | Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography | American National Standards Institute | |
Nuclear Regulatory Commission | 10 CFR 50.55a(h)(1) | IEEE 603 | 1991 | Standard Criteria for Safety Systems for Nuclear Power Generating Stations | Institute of Electrical and Electronics Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4) | ASME OM Code | 2004 | Code for Operation and Maintenance of Nuclear Power Plants | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 110.44(b)(1) | IAEA INFCIRC/225 | 1999 | Physical Protection of Nuclear Material and Nuclear Facilities | International Atomic Energy Agency | |
Nuclear Regulatory Commission | 10 CFR 34.20(e) | ANSI N432 | 1980 | Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography | American National Standards Institute | |
Nuclear Regulatory Commission | 87 FR 65128 | 10 CFR 50 | ASME NQA-1-2015 | 2015 | American Society of Mechanical Engineers 2019-2020 Code Editions | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(1) | ASME B&PV Code | 1980 | Boiler and Pressure Vessel Code, Section III, Division 2 | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xx)(B) | ASME B&PV Code | 2002 | Boiler and Pressure Vessel Code, Section XI, NDE provision in IWA-4540(a)(2) of the 2002 Addenda | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(g)(4)(ii) | NRC Regulatory Guide 1.147 | 2010 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16 | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 10 CFR 73.26(l)(1) | ANSI MH5.1 | 1971 | Basic Requirements for Cargo Containers | American National Standards Institute | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(4)(i) | NRC Regulatory Guide 1.84 | 2010 | Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 35 | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 10 CFR 73.50(d)(1) | FedSpec W-A-00450 B | 1973 | Alarm Systems, Interior, Security, Components for | Federal Specifications Standards and Test Methods | |
Nuclear Regulatory Commission | 87 FR 11934 | 10 CFR 50 | ASME OM | 2020 | Approval of American Society of Mechanical Engineers' Code Cases | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 34.20(e) | NIST Handbook 136 | 1981 | Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography | National Institute of Standards and Technology, U.S. Department of Commerce | |
Nuclear Regulatory Commission | 10 CFR 50.55a(d)(2)(iii) | NRC Regulatory Guide 1.84 | 2010 | Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 35 | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 89 FR 58039 | 10 CFR 50 | NRC RG 1.147 Rev. 21 | 2024 | American Society of Mechanical Engineers Code Cases and Update Frequency | U.S. Nuclear Regulatory Commission |
Nuclear Regulatory Commission | 10 CFR 34.20(a)(1) | NIST Handbook 136 | 1981 | Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography | National Institute of Standards and Technology, U.S. Department of Commerce | |
Nuclear Regulatory Commission | 10 CFR 50.55a(h)(1) | IEEE 279 | 1971 | Criteria for Protection Systems for Nuclear Generating Stations | Institute of Electrical and Electronics Engineers | |
Nuclear Regulatory Commission | 85 FR 14736 | 10 CFR 50 | ASME BPVC III | 2013 | Approval of American Society of Mechanical Engineers' Code Cases | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4)(i) | ASME OM Code | 2004 | Code for Operation and Maintenance of Nuclear Power Plants | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 85 FR 14736 | 10 CFR 50 | ASME BPVC XI-1 | 2018 | Approval of American Society of Mechanical Engineers' Code Cases | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1) | ASME B&PV Code | 1963 | Boiler and Pressure Vessel Code, Section III, and include the 1963 Edition through 1973 Winter Addenda, and the 1974 Edition (Division 1) through the 2004 Edition (Division 1) | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xxi)(A) | ASME B&PV Code | 1997 | Boiler and Pressure Vessel Code, Section XI, Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items B3.40 and B3.60 and Items B3.120 and B3.140 1998 Ed, 1999 Addenda - latest edition and addenda, Table IWB-3512-1 | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(C)(1) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 73.26(l)(1) | ISO 1496 | 1978 | General Cargo Containers | International Organization for Standardization | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(4)(ii) | NRC Regulatory Guide 1.84 | 2010 | Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 35 | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B | ASTM E185 | 1982 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | ASTM International | |
Nuclear Regulatory Commission | 87 FR 11934 | 10 CFR 50 | NUREG-2228 | 2020 | Approval of American Society of Mechanical Engineers' Code Cases | U.S. Nuclear Regulatory Commission |
Nuclear Regulatory Commission | 87 FR 65128 | 10 CFR 50 | ASME BPVC-III-1-2019 | 2019 | American Society of Mechanical Engineers 2019-2020 Code Editions | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.55a(e)(1) | ASME BPVC III | 2016 | Boiler and Pressure Vessel Code, Section III, Class 3 Components | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 89 FR 58039 | 10 CFR 50 | NRC RG 1.192 Rev. 5 | 2024 | American Society of Mechanical Engineers Code Cases and Update Frequency | U.S. Nuclear Regulatory Commission |
Nuclear Regulatory Commission | 10 CFR 50.73(b)(2)(ii)(F)(2) | IEEE 803 | 1983 | Recommended Practice for Unique Identification in Power Plants and Related Facilities | Institute of Electrical and Electronics Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4)(i) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
Nuclear Regulatory Commission | 85 FR 14736 | 10 CFR 50 | ASME BPVC OM | 2017 | Approval of American Society of Mechanical Engineers' Code Cases | American Society of Mechanical Engineers |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI including the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2004 Edition (Division 1) | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xxi)(B) | ASME B&PV Code | 1995 | Boiler and Pressure Vessel Code, Section XI, 1995 Edition and 1997 Addenda | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(C)(2) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 73.50(d)(1) | FedSpec W-A-00450 B | 1973 | Alarm Systems, Interior, Security, Components for | Federal Specifications Standards and Test Methods | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(5) | NRC Regulatory Guide 1.147 | 2010 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16 | U.S. Nuclear Regulatory Commission |