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Standards Incorporated by Reference (SIBR) Database
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Accessing Standards Incorporated by Reference
This database provides information on standards that have been cited or 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 | 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 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 | 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 | 10 CFR 50.55a(b)(3) | ASME OM Code | 2004 | Code for Operation and Maintenance of Nuclear Power Plants | American Society of Mechanical Engineers | |
| 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 | 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 | 87 FR 65128 | 10 CFR 50 | BPVC-XI-1-2020 | 2020 | American Society of Mechanical Engineers 2019-2020 Code Editions | 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 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 | 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 | 10 CFR 50.55a(h)(2) | IEEE 279 | 2010 | Criteria for Protection Systems for Nuclear Generating Stations | Institute of Electrical and Electronics Engineers | |
| 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 | 87 FR 65128 | 10 CFR 50 | BPVC-OM-IST-2020 | 2020 | American Society of Mechanical Engineers 2019-2020 Code Editions | American Society of Mechanical Engineers |
| Nuclear Regulatory Commission | 87 FR 11934 | 10 CFR 50 | ASME BPVC III, Revision 39 | 2015 | Approval of American Society of Mechanical Engineers' Code Cases | 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 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 | 85 FR 26540 | 10 CFR 50 | ASME BPVC III | 2017 | American Society of Mechanical Engineers 2015-2017 Code Editions Incorporation by Reference | American Society of Mechanical Engineers |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B | ASTM E 185 | 1982 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | ASTM International | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, IV | ASTM E 185 | 1982 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | ASTM International | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(e)(2) | ASME BPVC III | 2016 | Boiler and Pressure Vessel Code, Section III, paragraph NCA-1140, Subsection NCA | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(h)(2) | 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(b)(1)(ii) | ASME B&PV Code | 1989 | Boiler and Pressure Vessel Code, Section III, 1989 Addenda through the latest edition, and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4)(ii) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 87 FR 65128 | 10 CFR 50 | ASME OM Code Case OMN–28 | 2015 | American Society of Mechanical Engineers 2019-2020 Code Editions | 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 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 | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 2 | ASME BPVC III | 2020 | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(e)(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 | 10 CFR 50.55a(h)(3) | 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(b)(1)(iii) | ASME B&PV Code | 1993 | Boiler and Pressure Vessel Code, Section III, Articles NB-3200, NB-3600, NC-3600, and ND-3600 for seismic design of piping, up to and including the 1993 Addenda, but not the 1994 Addenda through the latest edition and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4)(ii) | NRC Regulatory Guide 1.147 | 2007 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16 | U.S. Nuclear Regulatory Commission | |
| Nuclear Regulatory Commission | 87 FR 65128 | 10 CFR 50 | ASME NQA–1b–2011 | 2011 | American Society of Mechanical Engineers 2019-2020 Code Editions | American Society of Mechanical Engineers |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xxii) | ASME B&PV Code | 2001 | Boiler and Pressure Vessel Code, Section XI, IWA-2220, Surface Examination, 2001 Edition through the latest edition and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(D)(1) | ASME Code Case N-729-1 | 2006 | Alternative Examination Requirements for PWR Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section XI, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(5)(i) | NRC Regulatory Guide 1.147 | 2010 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16 | U.S. Nuclear Regulatory Commission | |
| Occupational Safety and Health Administration | 29 CFR 1910.261(a)(3)(iii) | ANSI A17.1c | 1969 | Safety Code for Elevators, Dumbwaiters, and Moving Walks | American National Standards Institute | |
| Occupational Safety and Health Administration | 29 CFR 1910 Subpart L Appendix B 1910.158 | NFPA 21 | 1982 | Steam Fire Pumps | National Fire Protection Association | |
| Occupational Safety and Health Administration | 29 CFR 1926.6(h)(20) | ANSI J6.5 | 1971 | Rubber Insulating Sleeves | American National Standards Institute | |
| Occupational Safety and Health Administration | 29 CFR 1910 Subpart L Appendix B 1910.158 | NFPA 13E | 2010 | Fire Department Operations in Properties Protected by Sprinkler, Standpipe Systems | National Fire Protection Association | |
| Occupational Safety and Health Administration | 29 CFR 1928.51(b)(1) | 29 CFR 1928.52 | 2021 | Protective Frames for Wheel-type Agricultural Tractors--Test procedures and performance requirements | Occupational Safety and Health Administration, U.S. Department of Labor | |
| Occupational Safety and Health Administration | 29 CFR 1926.57(f)(5)(v)(A) | ANSI Z41.1 | 1967 | Men's Safety-Toe Footwear | American National Standards Institute | |
| Occupational Safety and Health Administration | 29 CFR 1918.101(a)(1)(ii) | ANSI Z87.1 | 1989 | Practice for Occupational and Educational Eye and Face Protection | American National Standards Institute | |
| Occupational Safety and Health Administration | 29 CFR 1926.1433(b)(1) | ANSI B30.5, 5-1.1.1 | 2004 | Safety Code for Crawler, Locomotive and Truck Cranes, Load Ratings—Where Stability Governs Lifting Performance”), paragraphs (a)-(d) (including subparagraphs) | American National Standards Institute |