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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 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) | 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)(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 | |
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(e)(2) | ASME B&PV Code | 0 | Boiler and Pressure Vessel Code, Section III, paragraph NCA-1140, Subsection NCA | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(e)(1) | ASME B&PV Code | 0 | Boiler and Pressure Vessel Code, Section III, Class 3 Components | American Society of Mechanical Engineers | |
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(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(d)(1) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section III, Class 2 Components | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(c)(3)(iv) | 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(c)(3) | ASME B&PV Code | 1980 | Boiler and Pressure Code, Section III, paragraph NCA-1140, Subsection NCA | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(c)(1) | ASME B&PV Code | 2004 | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(6)(iii) | 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(b)(6)(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(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 | 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 | |
Coast Guard | 10 CFR 50.55a(b)(5)(iii) | 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)(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 | 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 | 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 50.55a(b)(4)(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)(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 50.55a(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 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 50.55a(b)(3)(vi) | ASME OM Code | 1999 | Code for Operation and Maintenance of Nuclear Power Plants, ISTC-3540 of the 1999 Addenda through the latest edition and addenda | American Society of Mechanical Engineers | |
Nuclear Regulatory Commission | 10 CFR 50.55a(b)(3)(v) | ASME OM Code | 1995 | Code for Operation and Maintenance of Nuclear Power Plants, Subsection ISTD, Inservice Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Power Plants, 1995 Edition through the latest edition and addenda | American Society of Mechanical Engineers |