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Standards Incorporated by Reference (SIBR) Database
NOTE: This database has not been updated since August 16, 2016 and is being provided as a source for historical data. Data and information released from the Standards Incorporated by Reference databases at NIST are provided on an "AS IS" basis, without representation or warranty of any kind, including without limitation the warranties of merchantability, fitness for a particular purpose and non-infringement. Data and/or information may contain errors or be incomplete.
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| Incorporated by (Agency) | FR Citation | CFR Citation Sort descending | Document Number | Title of Standard | Standard Publishing Organization |
|---|---|---|---|---|---|
| Energy Department | 10 CFR 440 Appendix A | ASME B&PV Code | Boiler and Pressure Vessel Code, Section V | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 85 FR 62199 | 10 CFR 50 | ASTM E 185–82 | Reactor Vessel Material Surveillance Program | American Society for Testing and Materials |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, I | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, I | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, I | ASTM E 185 | Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 1 | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 1 | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 1 | ASTM E 185 | Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 2 | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, III, B, 2 | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50 App. H, IV | ASTM E 185 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels | American Society for Testing and Materials | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(1) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(1) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 2 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(2) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 1, Subsubarticle NE-3220, Service Level A Limits | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(2) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 1, Subsubarticle NE-3220, Service Level C Limits | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(A)(2) | ASME B&PV Code | Boiler Pressure Vessel Code, Section III, Division 2 Subsubarticle CC-3720, Factored Load Category | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(B)(1) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 1 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.34(f)(3)(v)(B)(1) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, Division 2 | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(1) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(2)(vii)(A) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(3)(i) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(3)(ii) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(4) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(c)(4)(i) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.48(f) | NFPA 805 | Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants | National Fire Protection Association | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(a)(2) | ASME OM Code | Boiler and Pressure Vessel Code, various editions | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b) | NRC Regulatory Guide 1.147 | 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) | NRC Regulatory Guide 1.84 | 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) | NRC Regulatory Guide 1.192 | Operation and Maintenance Code Case Acceptability, ASME OM Code | U.S. Nuclear Regulatory Commission | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| National Highway Traffic Safety Administration | 10 CFR 50.55a(b) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, and include the 1963 Edition through 1973 Winter Addenda, and the 1974 Edition (Division 1) through the 2004 Edition (Division 1) | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(i) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III, 1992 Edition with the 1992 Addenda of Section II | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(ii) | ASME B&PV Code | 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(b)(1)(iii) | ASME B&PV Code | 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(b)(1)(iv) | NCA-4000 | Quality Assurance Requirements for Nuclear Facilities, 1986 Edition through the 1992 Edition | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(iv) | NQA-1 | Quality Assurance Requirements for Nuclear Facilities, 1986 Edition through the 1992 Edition | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(iv) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(v) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section III | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(1)(vi) | ASME B&PV Code | 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 50.55a(b)(2) | ASME B&PV Code | 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)(2)(i) | ASME B&PV Code | 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(b)(2)(ii) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI, Table IWB-2500 and Table IWB-2600 Category B-J and the addenda through the Summer 1975 Addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(ix) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI, Subsection IWE, 1992 Edition with the 1992 Addenda, or the 1995 Edition with the 1996 Addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(vii) | ASME OM Code | Code for Operation and Maintenance of Nuclear Power Plants or 1989 Edition, Revision Date or Indicator for ASME/ANSI OM Part 4, ASME/ANSI Parts 6, and 10 must be the OMa-1988 Addenda to the OM-1987 Edition | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(vii) | ASME B&PV Code | 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(b)(2)(viii) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI, Division 1, Subsection IWL, 1992, 1995, 1998, and 2001 editions and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xii) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI, 1997 and later editions and addenda | American Society of Mechanical Engineers | |
| Nuclear Regulatory Commission | 10 CFR 50.55a(b)(2)(xiv) | ASME B&PV Code | Boiler and Pressure Vessel Code, Section XI, Appendix VIII, 1999 Addenda through the latest edition and addenda, VII-4240 of Appendix VII, 1999 and later editions and addenda | American Society of Mechanical Engineers |