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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 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(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 | 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 App. H, IV | ASTM E185 | 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)(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)(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)(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 | 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 | NUREG-2228 | 2020 | Approval of American Society of Mechanical Engineers' Code Cases | U.S. Nuclear Regulatory Commission |
| 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 52 App. B | DOE Publication | 1997 | System 80+ Design Control Document, ABB-CE | Combustion Engineering, Inc. | |
| 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 50.55a(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 | |
| 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 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(f)(2) | 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)(3) | ASME OM Code | 2004 | Code for Operation and Maintenance of Nuclear Power Plants | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(v) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(4)(ii) | ASME OM Code | 2004 | Code for Operation and Maintenance of Nuclear Power Plants | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(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(g)(6)(ii)(D)(3) | 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 | 89 FR 58039 | 10 CFR 50 | NRC NUREG-2228 | 2020 | American Society of Mechanical Engineers Code Cases and Update Frequency | U.S. Nuclear Regulatory Commission |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(5)(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 | 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 App. H, III, B, 2 | ASME BPVC XI | 2014 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(2) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
| 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 50.55a(b)(1)(vi) | ASME B&PV Code | 1995 | Boiler and Pressure Vessel Code, Section III and Addenda, Subsection NH, Class 1 Components in Elevated Temperature Service, 1995 Addenda through the latest edition and addenda | 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(f)(4)(ii) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
| Nuclear Regulatory Commission | 89 FR 70449 | 10 CFR 50 | ASME BPVC 2021 | 2021 | American Society of Mechanical Engineers 2021-2022 Code Editions | American Society of Mechanical Engineers |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xxiii) | ASME B&PV Code | 2001 | Boiler and Pressure Vessel Code, Section XI, Appendix VIII and the supplements to Appendix VIII and Article I-3000 of Section XI of 2002 Addenda through the latest edition and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(D)(4)(iv) | 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) | ASME BPV | 2016 | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(6) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(3)(iii)(A) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | 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)(2)(i) | ASME B&PV Code | 1974 | Boiler and Pressure Vessel Code, Section XI, 1974 Edition, addenda through the Summer 1975 Addenda, 1977 Edition, all of the addenda through the Summer 1978 Addenda, Addenda and editions subsequent to the Summer 1978 Addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(2) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(2)(vii)(A) | NFPA 805 | 2001 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xxiv) | ASME B&PV Code | 2002 | Boiler and Pressure Vessel Code, Section XI, Appendix VIII and the supplements to Appendix VIII and Article I-3000 of Section XI of 2002 Addenda through the latest edition and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(D)(5) | 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(a)(2) | ASME OM Code | 2020 | Boiler and Pressure Vessel Code, various editions | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(6)(i) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
| Nuclear Regulatory Commission | 88 FR 3287 | 10 CFR 52 | NuScale DCA, Rev. 5 | 2020 | NuScale Small Modular Reactor Design Certification | U.S. Nuclear Regulatory Commission |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(3)(iii)(A) | 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(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)(2)(vii) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section XI, Division 1, Table IWA-1600-1, Referenced Standards and Specifications, 1987 Addenda, 1988 Addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(2) | NRC Regulatory Guide 1.147 | 2010 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16 | U.S. Nuclear Regulatory Commission |