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Standards Incorporated by Reference (SIBR) Database
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NOTE: This database does not included records related to the Incorporation by Reference for the following: Department of Transportation, Federal Aviation Administration – Airworthiness Directives, State Air Plan Approvals, and Standard Instrumentation Approach Procedures; and the Environmental Protection Agency - State Approval of Air Quality Plans.
| Incorporated by (Agency) | FR Citation | CFR Citation Sort ascending | Document Number | Document Edition / Year | Title of Standard | Standard Publishing Organization |
|---|---|---|---|---|---|---|
| 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 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)(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) | 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)(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)(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 | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(f)(3)(iii)(A) | 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)(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)(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(f)(2) | NRC Regulatory Guide 1.192 | 2003 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission |