| 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(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(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)(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)(1) |
ASME BPVC III |
2016 |
Boiler and Pressure Vessel Code, Section III, Class 3 Components
|
American Society of Mechanical Engineers |
| Nuclear Regulatory Commission |
|
10 CFR 50.55a(e)(2) |
ASME BPVC III |
2016 |
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)(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(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 1.147 |
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) |
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)(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)(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)(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)(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)(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)(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(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(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)(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)(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)(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)(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)(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)(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)(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)(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)(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)(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)(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)(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)(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)(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(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 |