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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) | FR Citation | CFR Citation Sort ascending | Document Number | Document Edition / Year | Title of Standard | Standard Publishing Organization |
|---|---|---|---|---|---|---|
| Nuclear Regulatory Commission | 10 CFR 52 App. B | DOE Publication | 1997 | Tier 1, Tier 2, and Generic Technical Specifications | General Electric Co. | |
| Nuclear Regulatory Commission | 10 CFR 52 App. A, III A | DOE Publication | 1997 | U.S. ABWR Design Control Document | General Electric Co. | |
| National Highway Traffic Safety Administration | 10 CFR 52 App. A, III A | DOE Publication | 1997 | Tier 1, Tier 2, and Generic Technical Specifications | General Electric Co. | |
| National Highway Traffic Safety Administration | 10 CFR 52 App. A | DOE Publication | 1997 | Tier 1, Tier 2, and Generic Technical Specifications | General Electric Co. | |
| National Highway Traffic Safety Administration | 10 CFR 52 App. A | DOE Publication | 1997 | U.S. ABWR Design Control Document | General Electric Co. | |
| 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 50.73(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 50.73(b)(2)(ii)(F)(1) | 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(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(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(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(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(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(g)(6)(ii)(E)(3) | ASME Code Case N-722 | 2005 | Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 66/82/182 Materials, Section XI, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(E)(2) | ASME B&PV Code | 1980 | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(E)(2) | ASME Code Case N-722 | 2005 | Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 66/82/182 Materials, Section XI, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(E)(1) | ASME Code Case N-722 | 2005 | Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 66/82/182 Materials, Section XI, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(g)(6)(ii)(D)(6) | 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(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(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(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 | 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(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(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(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(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(g)(4)(i) | 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)(4)(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 | 10 CFR 50.55a(g)(4) | 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)(3)(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(g)(3)(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(g)(3)(i) | 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)(3)(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 | 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 50.55a(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 | |
| 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 | 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 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)(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 | 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 | 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 | 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 50.55a(f)(3)(iv)(B) | 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)(3)(iv)(B) | 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)(iv)(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(f)(3)(iv)(A) | 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 50.55a(f)(3)(iii)(B) | 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)(B) | 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)(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(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 |