This page lists the number, title, publication date, and revisions for each regulatory guide in Division 1, "Power Reactors," with references to draft guides and related documents (where applicable).
Guide
Number |
Title |
Rev. |
Publish
Date |
| 1.1 |
Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) |
-- |
11/1970 |
| 1.2 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.3 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors | 2 |
06/1974 |
| 1 |
06/1973 |
| -- |
11/1970 |
| 1.4 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors |
2 |
06/1974 |
| 1 |
06/1973 |
| -- |
11/1970 |
| 1.5 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) |
-- |
03/1971 |
| 1.6 |
Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6) |
-- |
03/1971 |
| 1.7 |
Control of Combustible Gas Concentrations in Containment
- DG-1117, Proposed Revision 3, published 08/2002
- Prior to the issuance of DG-1117, RG 1.7 was entitled "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," to reflect its narrower original scope
| 3 |
03/2007 |
| 2 |
11/1978 |
| 1 |
09/1976 |
| -- |
03/1971 |
|
1.8 |
Qualification and Training of Personnel for Nuclear Power Plants
- DG-1084, Second Proposed Revision 3, published 03/1999
- DG-1012, First Proposed Revision 3, published 09/1996
- Draft OL 403-5, Third Proposed Revision 2, published 01/1985
- Draft RS 807-5, Second Proposed Revision 2, published 09/1980
- Draft RS 807-5, First Proposed Revision 2, published 02/1979
| 3 |
05/2000 |
| 2 |
04/1987 |
| 1-R |
05/1977 |
| 1 |
09/1975 |
| -- |
03/1971 |
| 1.9 |
Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants
- DG-1172, Proposed Revision 4, published 11/2006
- Staff's responses to public comments on DG-1172
- Prior to the issuance of DG-1172, RG 1.9 was entitled "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants"
- DG-1021, Second Proposed Revision 3, published 04/1992
- Draft RS 802-5, First Proposed Revision 3, published 11/1988
|
4 |
03/2007 |
| 3 |
07/1993 |
| 2 |
12/1979 |
| 1 |
11/1978 |
| -- |
03/1971 |
| 1.10 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.11 |
Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) Supplement to Safety Guide 11, Backfitting Considerations |
-- |
03/1971 |
| 1.12 |
Nuclear Power Plant Instrumentation for Earthquakes
- DG-1033, Third Proposed Revision 2, published 02/1995
- DG-1016, Second Proposed Revision 2, published 11/1992
- Draft MS 140-5, First Proposed Revision 2, published 07/1981
|
2 |
03/1997 |
| 1 |
04/1974 |
| -- |
03/1971 |
| 1.13 |
Spent Fuel Storage Facility Design Basis
- DG-1162, Second Proposed Revision 2, published 10/2006
- Staff's responses to public comments on DG-1162
- Draft CE 913-5, First Proposed Revision 2, published 12/1981
- Revision 1 was issued for public comment on 12/1975
|
2 |
03/2007 |
| 1 |
12/1975 |
| -- |
03/1971 |
| 1.14 |
Reactor Coolant Pump Flywheel Integrity |
1 |
08/1975 |
| -- |
10/1971 |
| 1.15 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.16 |
Reporting of Operating Information -- Appendix A Technical Specifications (for Comment) |
4 |
08/1975 |
| 3 |
01/1975 |
| 2 |
09/1974 |
| 1 |
10/1973 |
| -- |
10/1971 |
| 1.17 |
(Withdrawn -- See 56 FR 30777, 07/5/1991) |
-- |
-- |
| 1.18 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.19 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.20 |
Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing |
3 |
03/2007 |
| 2 |
05/1976 |
| 1 |
06/1975 |
| -- |
12/1971 |
1.21
|
Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants |
1 |
06/1974 |
| -- |
12/1971 |
| 1.22 |
Periodic Testing of Protection System Actuation Functions (Safety Guide 22) |
-- |
02/1972 |
| 1.23 |
Meteorological Monitoring Programs for Nuclear Power Plants
- DG-1164, Third Proposed Revision 1, published 10/2006
- Staff's responses to public comments on DG-1164
- Draft ES 926-4, Second Proposed Revision 1, entitled "Meteorological Measurement Program for Nuclear Power Plants," published 04/1986
- Draft SS 926-4, First Proposed Revision 1, entitled "Meteorological Programs In Support of Nuclear Power Plants," published 09/1980
- Revision 0, entitled "Onsite Meteorological Programs," was issued as Safety Guide 23
| 1 |
03/2007 |
| -- |
02/1972 |
| 1.24 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide 24) |
-- |
03/1972 |
| 1.25 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25) |
-- |
03/1972 |
| 1.26 |
Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
- DG-1152, Proposed Revision 4, published 11/2006; no comments received
- Revision 3 was issued for public comment on 02/1976
|
4 |
03/2007 |
| 3 |
02/1976 |
| 2 |
06/1975 |
| 1 |
09/1974 |
| -- |
03/1972 |
| 1.27 |
Ultimate Heat Sink for Nuclear Power Plants (for Comment) |
2 |
01/1976 |
| 1 |
03/1974 |
| -- |
03/1972 |
| 1.28 |
Quality Assurance Program Requirements (Design and Construction)
- DG-1010, Proposed Revision 4, published 11/1992
- Draft RS 002-5, Proposed Revision 3, published 03/1981
|
3 |
08/1985 |
| 2 |
02/1979 |
| 1 |
03/1978 |
| -- |
06/1972 |
| 1.29 |
Seismic Design Classification |
4 |
03/2007 |
| 3 |
09/1978 |
| 2 |
02/1976 |
| 1 |
08/1973 |
| -- |
06/1972 |
| 1.30 |
Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) |
-- |
08/1972 |
|
1.31 |
Control of Ferrite Content in Stainless Steel Weld Metal |
3 |
04/1978 |
| 2 |
05/1977 |
| 1 |
06/1973 |
| -- |
08/1972 |
| 1.32 |
Criteria for Power Systems for Nuclear Power Plants
- DG-1079, Proposed Revision 3, published 04/2003
|
3 |
03/2004 |
| 2 |
02/1977 |
| 1 |
03/1976 |
| -- |
08/1972 |
|
1.33 |
Quality Assurance Program Requirements (Operation)
- Draft RS 902-4, Second Proposed Revision 3, published 11/1980
- Draft RS 902-4, First Proposed Revision 3, published 08/1979
|
2 |
02/1978 |
| 1 |
02/1977 |
| -- |
11/1972 |
| 1.34 |
Control of Electroslag Weld Properties |
-- |
12/1972 |
| 1.35 |
Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments
- Draft SC 810-4, Proposed Revision 0, published 04/1979
|
3 |
07/1990 |
| 2 |
01/1976 |
| 1 |
06/1974 |
| -- |
02/1973 |
| 1.35.1 |
Determining Prestressing Forces for Inspection of Prestressed Concrete Containments
- Draft SC 807-4, Proposed Revision 0, published 04/1979
|
-- |
07/1990 |
|
1.36 |
Nonmetallic Thermal Insulation for Austenitic Stainless Steel |
-- |
02/1973 |
| 1.37 |
Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants |
1 |
03/2007 |
| -- |
03/1973 |
| 1.38 |
Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants |
2 |
05/1977 |
| 1 |
10/1976 |
| -- |
03/1973 |
| 1.39 |
Housekeeping Requirements for Water-Cooled Nuclear Power Plants |
2 |
09/1977 |
| 1 |
10/1976 |
| -- |
03/1973 |
| 1.40 |
Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants |
-- |
03/1973 |
| 1.41 |
Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments |
-- |
03/1973 |
| 1.42 |
(Withdrawn -- See 41 FR 11891, 03/22/1976) |
-- |
-- |
| 1.43 |
Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components |
-- |
05/1973 |
| 1.44 |
Control of the Use of Sensitized Stainless Steel |
-- |
05/1973 |
| 1.45 |
Guidance on Monitoring and Responding to Reactor Coolant System Leakage
- Prior to the issuance of Revision 1, RG 1.45 was entitled "Reactor Coolant Pressure Boundary Leakage Detection Systems"
|
1 |
05/2008 |
| -- |
05/1973 |
| 1.46 |
(Withdrawn -- See 50 FR 9732, 03/11/1985) |
-- |
-- |
| 1.47 |
Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems |
-- |
05/1973 |
| 1.48 |
(Withdrawn -- See 50 FR 9732, 03/11/1985) |
-- |
-- |
| 1.49 |
(Withdrawn -- See 72 FR 36737, 07/05/2007) |
-- |
-- |
| 1.50 |
Control of Preheat Temperature for Welding of Low-Alloy Steel |
-- |
05/1973 |
| 1.51 |
(Withdrawn -- See 40 FR 30510, 07/21/1975) |
-- |
-- |
1.52
|
Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
- DG-1102, Proposed Revision 3, published 10/2000
|
3 |
06/2001 |
| 2 |
03/1978 |
| 1 |
07/1976 |
| -- |
06/1973 |
| 1.53 |
Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems
- DG-1118, Proposed Revision 1, published 05/2002
|
2 |
11/2003 |
| 1 |
10/2003 |
| -- |
06/1973 |
|
1.54 |
Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants
- DG-1976, Proposed Revision 1, published 03/1999
|
1 |
07/2000 |
| -- |
06/1973 |
| 1.55 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.56 |
Maintenance of Water Purity in Boiling Water Reactors (for Comment) |
1 |
07/1978 |
| -- |
06/1973 |
| 1.57 |
Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components |
1 |
03/2007 |
| -- |
06/1973 |
| 1.58 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.59 |
Design Basis Floods for Nuclear Power Plants
- Errata to Revision 2, published 07/30/1980
|
2 |
08/1977 |
| 1 |
04/1976 |
| -- |
08/1973 |
| 1.60 |
Design Response Spectra for Seismic Design of Nuclear Power Plants |
1 |
12/1973 |
| -- |
10/1973 |
1.61
|
Damping Values for Seismic Design of Nuclear Power Plants |
1 |
03/2007 |
| -- |
10/1973 |
| 1.62 |
Manual Initiation of Protective Actions |
-- |
10/1973 |
| 1.63 |
Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
- Draft EE 405-4, Proposed Revision 3, published 06/1986
|
3 |
02/1987 |
| 2 |
07/1978 |
| 1 |
05/1977 |
| -- |
10/1973 |
| 1.64 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.65 |
Materials and Inspections for Reactor Vessel Closure Studs |
-- |
10/1973 |
| 1.66 |
(Withdrawn -- See 42 FR 54478, 10/6/1977) |
-- |
-- |
| 1.67 |
(Withdrawn -- See 48 FR 19101, 04/27/1983) |
-- |
-- |
| 1.68 |
Initial Test Programs for Water-Cooled Nuclear Power Plants
|
3 |
03/2007 |
| 2 |
08/1978 |
| 1 |
01/1977 |
| -- |
11/1973 |
| 1.68.1 |
Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants |
1 |
01/1977 |
| -- |
12/1975 |
| 1.68.2 |
Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants |
1 |
07/1978 |
| -- |
01/1977 |
| 1.68.3 |
Preoperational Testing of Instrument and Control Air Systems
- Draft RS 709-4, a proposed revision to RG 1.80, published 10/1980
|
-- |
04/1982 |
| 1.69 |
Concrete Radiation Shields for Nuclear Power Plants |
-- |
12/1973 |
| 1.70 |
Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) |
3 |
11/1978 |
| 2 |
09/1975 |
| 1 |
10/1972 |
| -- |
02/1972 |
| 1.71 |
Welder Qualification for Areas of Limited Accessibility |
1 |
03/2007 |
| -- |
12/1973 |
1.72
|
Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin |
2 |
11/1978 |
| 1 |
01/1978 |
| -- |
12/1973 |
| 1.73 |
Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants |
-- |
01/1974 |
| 1.74 |
(Withdrawn -- See 54 FR 38919, 09/21/1989) |
-- |
-- |
| 1.75 |
Physical Independence of Electric Systems |
3 |
02/2005 |
| 2 |
09/1978 |
| 1 |
01/1975 |
| -- |
02/1974 |
| 1.76 |
Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants |
1 |
03/2007 |
| -- |
04/1974 |
| 1.77 |
Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors |
-- |
05/1974 |
| 1.78 |
Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release
- DG-1087, Proposed Revision 1, published 02/2001
- Revision 1 incorporates guidance from withdrawn Regulatory Guide 1.95
|
1 |
12/2001 |
| -- |
06/1974 |
| 1.79 |
Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors |
1 |
09/1975 |
| -- |
06/1974 |
| 1.80 |
(Withdrawn -- See 47 FR 19258, 05/4/1982)
- Reissued as Regulatory Guide 1.68.3, a renumbered revision of this guide, with an expanded scope that addresses control air systems (see details above)
|
-- |
-- |
| 1.81 |
Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants |
1 |
01/1975 |
| -- |
06/1974 |
| 1.82 |
Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident
- DG-1038, Proposed Revision 2, published 07/1995
- Draft MS 203-4, Proposed Revision 1, published 05/1983
|
3 |
11/2003 |
| 2 |
05/1996 |
| 1 |
11/1985 |
| -- |
06/1974 |
| 1.83 |
Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes |
1 |
07/1975 |
| -- |
06/1974 |
| 1.84 |
Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
- DG-1124, Proposed Revision 33, published 04/2004
- DG-1090, Proposed Revision 32, published 12/2001 (combined RG 1.84 and 1.85)
- DG-1049, Proposed Revision 31, published 05/1997
|
34 |
10/2007 |
33
32
31
30
29
28
27
26
25
24
23
22
21
20
19
18
17
16
15
14
13
12
11
10
9
8
7
6
5
4
3
2
1
-- |
08/2005
06/2003
05/1999
10/1994
07/1993
04/1992
11/1990
07/1989
05/1998
06/1986
09/1985
07/1984
09/1983
11/1982
04/1982
08/1981
12/1980
05/1980
05/1979
11/1978
07/1978
03/1978
11/1977
08/1977
03/1977
08/1976
05/1976
03/1976
11/1975
09/1975
06/1975
04/1975
06/1974 |
| 1.85 |
(Withdrawn 06/2003)
- Guidance from Revision 31 of RG 1.85 (Materials Code Case Acceptability -- ASME Section III, Division 1) was incorporated into Revision 32 of RG 1.84, published 06/2003; see the notice of withdrawal and details on RG 1.84 (above)
|
31 |
05/1999 |
1.86
|
Termination of Operating Licenses for Nuclear Reactors |
-- |
06/1974 |
| 1.87 |
Guidance for Construction of Class 1 Components in Elevated-Temperature Reactors
- Supplement to ASME Section III Code Cases 1592, 1593, 1594, 1595, and 1596
|
-- |
06/1975 |
| 1.88 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.89 |
Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants
- Draft EE 042-2, Proposed Revision 1, published 02/1982
|
1 |
06/1984 |
| -- |
11/1974 |
| 1.90 |
Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons |
1 |
08/1977 |
| -- |
11/1974 |
| 1.91 |
Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants |
1 |
02/1978 |
| -- |
01/1975 |
| 1.92 |
Combining Modal Responses and Spatial Components in Seismic Response Analysis
- DG-1127, Second Proposed Revision 2, published 02/2005
- DG-1108, First Proposed Revision 2, published 08/2001
|
2 |
07/2006 |
| 1 |
02/1976 |
| -- |
12/1974 |
| 1.93 |
Availability of Electric Power Sources |
-- |
12/1974 |
| 1.94 |
Quality Assurance Requirements for
Installation, Inspection, and Testing of Structural Concrete and
Structural Steel During the Construction Phase of Nuclear Power Plants
- Draft RS 908-5, Proposed Revision 2, published
09/1979
|
1 |
04/1976 |
| -- |
04/1975 |
| 1.95 |
(Withdrawn January 2002)
- Guidance from RG 1.95 (Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release) was incorporated into Revision 1 of RG 1.78, published 01/2002; see the notice of withdrawal and details on RG 1.78 (above)
|
-- |
-- |
| 1.96 |
Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants |
1 |
06/1976 |
| -- |
05/1975 |
| 1.97 |
Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants
- DG-1128, Proposed Revision 4, published 08/2005
- Revision 2 Errata, published 07/1981
- Draft RS 917-4, Proposed Revision 2, published 12/1979
- Prior to the issuance of Revision 1, RG 1.97 was entitled "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident"
|
4 |
06/2006 |
| 3 |
05/1983 |
| 2 |
12/1980 |
| 1 |
08/1977 |
| -- |
12/1975 |
| 1.98 |
Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment) |
-- |
03/1976 |
| 1.99 |
Radiation Embrittlement of Reactor Vessel Materials
- Draft ME 305-4, Proposed Revision 2, published 02/1986
|
2 |
05/1988 |
| 1 |
04/1977 |
| -- |
07/1975 |
| 1.100 |
Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants
- Draft EE 108-5, Proposed Revision 2, published 08/1987
|
2 |
06/1988 |
| 1 |
08/1977 |
| -- |
03/1976 |
1.101 |
Emergency Planning and Preparedness for Nuclear Power Reactors
- DG-1075, Proposed Revision 4, published 03/2000
- DG-1022, Proposed Revision 3, published 02/1992
- Revision 1 to this guide, entitled "Emergency Planning for Nuclear Power Plants," was withdrawn (see 45 FR 69610, 10/21/1980)
|
5 |
06/2005 |
| 4 |
07/2003 |
| 3 |
08/1992 |
| 2 |
10/1981 |
| 1 |
03/1977 |
| -- |
11/1975 |
| 1.102 |
Flood Protection for Nuclear Power Plants |
1 |
09/1976 |
| -- |
10/1975 |
| 1.103 |
(Withdrawn -- See 46 FR 37579, 07/21/1981) |
-- |
-- |
| 1.104 |
(Withdrawn -- See 44 FR 49321, 08/22/1979)
- See NUREG-0554, "Single-Failure-Proof Cranes for Nuclear Power Plants"
|
-- |
-- |
1.105
|
Setpoints for Safety-Related Instrumentation
- DG-1045, Proposed Revision 3, published 10/96
- Draft IC 010-5, Proposed Revision 2, published 12/81
|
3 |
12/1999 |
| 2 |
02/1986 |
| 1 |
11/1976 |
| -- |
11/1975 |
| 1.106 |
Thermal Overload Protection for Electric Motors on Motor-Operated Valves |
1 |
03/1977 |
| -- |
11/1975 |
| 1.107 |
Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures |
1 |
02/1977 |
| -- |
11/1975 |
| 1.108 |
(Withdrawn -- See 58 FR 41813, 08/5/1993)
- Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
|
-- |
-- |
| 1.109 |
Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I |
1 |
10/1977 |
| -- |
03/1976 |
| 1.110 |
Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (for Comment) |
-- |
03/1976 |
1.111
|
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors |
1 |
07/1977 |
| -- |
03/1976 |
1.112
|
Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors |
1 |
03/2007 |
| 0-R |
05/1977 |
| -- |
04/1976 |
| 1.113 |
Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I |
1 |
04/1977
(2.18MB) |
| -- |
05/1976 |
| 1.114 |
Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit |
3 |
10/2008 |
| 2 |
05/1989 |
| 1 |
11/1976 |
| -- |
02/1976 |
| 1.115 |
Protection Against Low-Trajectory Turbine Missiles |
1 |
07/1977 |
| -- |
03/1976 |
| 1.116 |
Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems |
0-R |
05/1977 |
| -- |
06/1976 |
| 1.117 |
Tornado Design Classification |
1 |
04/1978 |
| -- |
06/1976 |
| 1.118 |
Periodic Testing of Electric Power and Protection Systems
- DG-1028, Proposed Revision 3, published 09/1994
|
3 |
04/1995 |
| 2 |
06/1978 |
| 1 |
11/1977 |
| -- |
06/1976 |
| 1.119 |
(Withdrawn -- See 42 FR 33387, 06/30/1977) |
-- |
-- |
1.120
|
(Withdrawn 08/15/01)
- Revision 0, "Fire Protection Guidelines for Nuclear Power Plants," published 06/1976
- Revision 1, published 11/1977, was subsequently withdrawn 08/15/01
|
-- |
-- |
| -- |
-- |
| 1.121 |
Bases for Plugging Degraded PWR Steam Generator Tubes (for Comment) |
-- |
08/1976 |
1.122
|
Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components |
1 |
02/1978 |
| -- |
09/1976 |
| 1.123 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.124 |
Service Limits and Loading Combinations for Class 1 Linear-Type Supports |
2 |
02/2007 |
| 1 |
01/1978 |
| -- |
11/1976 |
| 1.125 |
Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants |
2 |
03/2009 |
| 1 |
10/1978 |
| -- |
03/1977 |
| 1.126 |
An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification |
1 |
03/1978 |
| -- |
03/1977 |
| 1.127 |
Inspection of Water-Control Structures Associated with Nuclear Power Plants |
1 |
03/1978 |
| -- |
04/1977 |
| 1.128 |
Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants
- DG-1154, Proposed Revision 2, published 10/2006
- Staff's responses to public comments on DG-1154
- Prior to the issuance of DG-1154, RG 1.128 was entitled "Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants"
|
2 |
02/2007 |
| 1 |
10/1978 |
| -- |
04/1977 |
| 1.129 |
Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants
- DG-1155, Proposed Revision 2, published 10/2006
- Staff's responses to public comments on DG-1155
- Prior to the issuance of DG-1155, RG 1.129 was entitled "Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants"
|
2 |
02/2007 |
| 1 |
02/1978 |
| -- |
04/1977 |
| 1.130 |
Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports
|
2 |
03/2007 |
| 1 |
10/1978 |
| -- |
07/1977 |
| 1.131 |
Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (for Comment)
(Withdrawn -- See 74 FR 18000, 04/20/2009)
Replaced by guidance in Regulatory Guide 1.211. |
-- |
08/1977 |
| 1.132 |
Site Investigations for Foundations of Nuclear Power Plants
- DG-1101, Proposed Revision 2, published 02/2001
|
2 |
10/2003 |
| 1 |
03/1979 |
| -- |
09/1977 |
| 1.133 |
Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors |
1 |
05/1981 |
| -- |
09/1977 |
| 1.134 |
Medical Evaluation of Licensed Personnel at Nuclear Power Plants
- DG-1068, Proposed Revision 3, published 02/1997
- Draft OL 401-5, Proposed Revision 2, published 11/1984
|
3 |
03/1998 |
| 2 |
04/1987 |
| 1 |
03/1979 |
| -- |
09/1977 |
| 1.135 |
Normal Water Level and Discharge at Nuclear Power Plants (for Comment) |
-- |
09/1977 |
| 1.136 |
Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments
- DG-1159, Proposed Revision 3, published 10/2006
- Staff's responses to public comments on DG-1159
- Prior to the issuance of DG-1159, RG 1.136 was entitled "Materials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through ‑6000 of the 'Code for Concrete Reactor Vessels and Containments')"
- Draft SC 814-5, Proposed Revision 2, published 11/1979
|
3 |
03/2007 |
| 2 |
06/1981 |
| 1 |
10/1978 |
| -- |
11/1977 |
| 1.137 |
Fuel-Oil Systems for Standby Diesel Generators |
1 |
10/1979 |
| -- |
01/1978 |
| 1.138 |
Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants
- Revision 1 was not published
- DG-1109, Proposed Revision 1, published 08/2001
|
2 |
12/2003 |
| 1 |
-- |
| -- |
04/1978 |
| 1.139 |
Guidance for Residual Heat Removal (for Comment)
(Withdrawn -- See 73 FR 32750, 06/10/2008) |
-- |
05/1978 |
|
1.140 |
Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
- DG-1103, Proposed Revision 2, issued 10/2000
|
2 |
06/2001 |
| 1 |
10/1979 |
| -- |
03/1978 |
| 1.141 |
Containment Isolation Provisions for Fluid Systems (for Comment) |
-- |
04/1978 |
|
1.142 |
Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)
- DG-1098, Proposed Revision 2, published 08/2000
|
2 |
11/2001 |
| 1 |
10/1981 |
| -- |
04/1978 |
|
1.143 |
Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants
- DG-1100, Proposed Revision 2, published 08/2000
|
2 |
11/2001 |
| 1 |
10/1979 |
| -- |
07/1978 |
| 1.144 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.145 |
Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants
- Reissued 02/1983 to correct page 1.145-7
|
1 |
02/1983 |
| -- |
08/1979 |
| 1.146 |
(Withdrawn -- See 56 FR 36175, 07/31/1991) |
-- |
-- |
| 1.147 |
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1
- DG-1125, Proposed Revision 14, published 08/2004
- Corrected reprint of Revision 13 (Rev. 13-R), published 01/2004
- DG-1091, Proposed Revision 13, published 12/2001
- DG-1050, Proposed Revision 12, published 05/1997
- Draft SC 721-4, Proposed Revision 0, published 08/1979
|
15 |
10/2007 |
14
13-R
13
12
11
10
99
8
7
6
5
4
3
2
1
-- |
08/2005
01/2004
06/2003
05/1999
10/1994
07/1993
04/1992
11/1990
07/1989
05/1988
08/1986
09/1985
07/1984
06/1983
--
03/1981 |
| 1.148 |
Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants
- Draft SC 704-5, Proposed Revision 0, published 02/1979
|
-- |
03/1981 |
|
1.149 |
Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations
- DG-1080, Proposed Revision 3, published 08/1999
- DG-1043, Proposed Revision 2, published 06/1995
- Draft OL 402-5, Proposed Revision 1, published 11/1984
- Draft RS 110-5, Proposed Revision 0, 07/1980
|
3 |
10/2001 |
| 2 |
04/1996 |
| 1 |
04/1987 |
| -- |
04/1981 |
| 1.150 |
(Withdrawn-- See 73 FR 7766, 02/11/2008) |
-- |
-- |
| 1.151 |
Instrument Sensing Lines
- Draft IC 126-5, Proposed Revision 0, published 03/1982
|
-- |
07/1983 |
| 1.152 |
Criteria for Digital Computers in Safety Systems of Nuclear Power Plants
- DG-1130, Proposed Revision 2, published 12/2004
- DG-1039, Proposed Revision 1, published 05/1995
- Draft IC 127-5, Proposed Revision 0, published 03/1983
|
2 |
01/2006 |
| 1 |
01/1996 |
| -- |
11/1985 |
| 1.153 |
Criteria for Safety Systems (12/85)
- DG-1042, Proposed Revision 1, published 11/1995
- Draft IC 609-5, Proposed Revision 0, published 12/1982
|
1 |
06/1996 |
| -- |
12/1985 |
| 1.154 |
Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
- Draft SI 502-4, Proposed Revision 0, published 01/1986
|
-- |
01/1987 |
| 1.155 |
Station Blackout
- Revision 0, issued June 1988, and reissued August 1988 with corrected tables
- Draft SI 501-4, Proposed Revision 0, published 03/1986
|
-- |
08/1988 |
| 1.156 |
Environmental Qualification of Connection Assemblies for Nuclear Power Plants
- Draft EE 404-4, Proposed Revision 0, published 05/1987
|
-- |
11/1987 |
| 1.157 |
Best-Estimate Calculations of Emergency Core Cooling System Performance
- Draft RS 701-4, Proposed Revision 0, published 03/1987
|
-- |
05/1989 |
| 1.158 |
Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants
- Draft EE 006-5, Proposed Revision 0, published 08/1987
|
-- |
02/1989 |
| 1.159 |
Assuring the Availability of Funds for Decommissioning Nuclear Reactors
- DG-1106, Proposed Revision 1, published 05/2001
- DG-1003, Proposed Revision 0, published 05/1989
|
1 |
10/2003 |
| -- |
08/1990 |
| 1.160 |
Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
- DG-1051, Proposed Revision 2, published 08/1996
- DG-1031, Proposed Revision 1, published 06/1994
- DG-1020, Proposed Revision 0, published 11/1992
|
2 |
03/1997 |
| 1 |
01/1995 |
| -- |
06/1993 |
| 1.161 |
Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb
- DG-1023, Proposed Revision 0, published 09/1993
|
-- |
06/1995 |
| 1.162 |
Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels
- DG-1027, Proposed Revision 0, published 10/1994
|
-- |
02/1996 |
| 1.163 |
Performance-Based Containment Leak-Test Program
- Errata to NEI 94-01, published 03/1996
- DG-1037, Proposed Revision 0, published 02/1995
|
-- |
09/1995 |
| 1.164 |
(Not yet issued) |
|
|
| 1.165 |
Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion
- DG-1032, Second Proposed Revision 0, published 02/1995
- DG-1015, First Proposed Revision 0, published 11/1992
|
-- |
03/1997 |
| 1.166 |
Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions
- DG-1034, Second Proposed Revision 0, published 02/1995
- DG-1017, First Proposed Revision 0, published 11/1992
|
-- |
03/1997 |
| 1.167 |
Restart of a Nuclear Power Plant Shut Down by a Seismic Event
- DG-1035, Second Proposed Revision 0, published 02/1995
- DG-1018, First Proposed Revision 0, published 11/1992
|
-- |
03/1997 |
| 1.168 |
Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1123, Proposed Revision 1, published 01/2003
- DG-1054, Proposed Revision 0, published 08/1996
|
1 |
02/2004 |
| -- |
09/1997 |
| 1.169 |
Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1055, Proposed Revision 0, published 08/1996
|
-- |
09/1997 |
| 1.170 |
Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1056, Proposed Revision 0, published 08/1996
|
-- |
09/1997 |
| 1.171 |
Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1057, Proposed Revision 0, published 08/1996
|
-- |
09/1997 |
| 1.172 |
Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1058, Proposed Revision 0, 08/1996
|
-- |
09/1997 |
| 1.173 |
Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants
- DG-1059, Proposed Revision 0, published 08/1996
|
-- |
09/1997 |
1.174
|
An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis
- Revision 1 issued with SRP Chapter 19
- DG-1110, Proposed Revision 1, published 06/2001
- DG-1061, Proposed Revision 0, published 06/1997
|
1 |
11/2002 |
| -- |
07/1998 |
| 1.175 |
An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing
- Revision 0 issued with SRP Chapter 3.9.7
- DG-1062, Proposed Revision 0, published 06/1997
|
-- |
08/1998 |
| 1.176 |
(Withdrawn-- See 73 FR 7766, 02/11/2008) |
-- |
-- |
| 1.177 |
An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications
- Revision 0 issued with SRP Chapter 16.1
- DG-1065, Proposed Revision 0, published 06/1997
|
-- |
08/1998 |
|
1.178 |
An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping |
1 |
09/2003 |
| -- |
09/1998 |
| 1.179 |
Standard Format and Content of License Termination Plans for Nuclear Power Reactors
- DG-1078, Proposed Revision 0, published 04/1998
|
-- |
01/1999 |
1.180
|
Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems
- DG-1119, Proposed Revision 1, published 08/2002
- DG-1029, Proposed Revision 0, published 02/1998
|
1 |
10/2003 |
| -- |
01/2000 |
1.181
|
Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)
- DG-1083, Proposed Revision 0, published 03/1999
|
-- |
09/1999 |
| 1.182 |
Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants
- DG-1082, Proposed Revision 0, published 12/1999
|
-- |
05/2000 |
|
1.183 |
Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
- DG-1081, Proposed Revision 0, published 12/1999
|
-- |
07/2000 |
| 1.184 |
Decommissioning of Nuclear Power Reactors
- Errata to update Reference 1, published 04/2004
- DG-1067, Proposed Revision 0, published 06/1997
|
-- |
07/2000 |
| 1.185 |
Standard Format and Content for Post-Shutdown Decommissioning Activities Report
- Errata to update Reference 1, published 04/2004
- DG-1071, Proposed Revision 0, published 12/1997
|
-- |
07/2000 |
|
1.186 |
Guidance and Examples for Identifying 10 CFR 50.2 Design Bases
- DG-1093, Proposed Revision 0, published 04/2000
|
-- |
12/2000 |
|
1.187 |
Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments
- DG-1095, Proposed Revision 0, published 04/2000
|
-- |
11/2000 |
1.188
|
Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses
- DG-1140, Proposed Revision 1, published 01/2005
- DG-1104, Third Proposed Revision 0, published 08/2000
- DG-1047, Second Proposed Revision 0, published 08/1996
- DG-1009, First Proposed Revision 0, published 12/1990
|
1 |
09/2005 |
| -- |
07/2001 |
| 1.189 |
Fire Protection for Nuclear Power Plants
- DG-1170, Proposed Revision 1, published 11/2006
- Staff's responses to public comments on DG-1170, DG-1097, and DG-1094
- Prior to the issuance of DG-1170, RG 1.189 was entitled "Fire Protection for Operating Nuclear Power Plants"
- DG-1097, Second Proposed Revision 0, published 06/2000
- DG-1094, First Proposed Revision 0, published 10/1999
|
1 |
03/2007 |
| -- |
04/2001 |
| 1.190 |
Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
- DG-1053, Second Proposed Revision 0, published 09/1999
- DG-1025, First Proposed Revision 0, published 09/1993
|
-- |
03/2001 |
|
1.191 |
Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown
- DG-1069, Proposed Revision 0, published 07/1998
|
-- |
05/2001 |
| 1.192 |
Operation and Maintenance Code Case Acceptability, ASME OM Code
- DG-1089, Proposed Revision 0, published 12/01
|
-- |
06/2003 |
| 1.193 |
ASME Code Cases Not Approved for Use
- DG-1126, Proposed Revision 1, published 08/2004
- DG-1112, Proposed Revision 0, published 12/2001
|
2 |
10/2007 |
| 1 |
08/2005 |
| -- |
06/2003 |
| 1.194 |
Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants
- DG-1111, Proposed Revision 0, published 12/2001
|
-- |
06/2003 |
| 1.195 |
Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors
- DG-1113, Proposed Revision 0, published 01/2002
|
-- |
05/2003 |
| 1.196 |
Control Room Habitability at Light-Water Nuclear Power Reactors
- DG-1114, Proposed Revision 0, published 03/2002
|
1 |
01/2007 |
| -- |
05/2003 |
| 1.197 |
Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors
- DG-1115, Proposed Revision 0, published 03/2002
|
-- |
05/2003 |
| 1.198 |
Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites
- DG-1105, Proposed Revision 0, published 03/2001
|
-- |
11/2003 |
| 1.199 |
Anchoring Components and Structural Supports in Concrete
- DG-1099, Proposed Revision 0, published 07/2002
|
-- |
11/2003 |
| 1.200 |
An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities |
2 |
03/2009 |
| 1 |
01/2007 |
| -- |
02/2004 |
| 1.201 |
Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance
- DG-1121, Proposed Revision 0, published 05/2003
|
1 |
05/2006 |
| -- |
01/2006 |
| 1.202 |
Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors
- DG-1085, Proposed Revision 0, published 11/2001
|
-- |
02/2005 |
| 1.203 |
Transient and Accident Analysis Methods |
-- |
12/2005 |
| 1.204 |
Guidelines for Lightning Protection of Nuclear Power Plants
- DG-1137, Proposed Revision 0, published 02/2005
|
-- |
11/2005 |
| 1.205 |
Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
- DG-1139, Proposed Revision 0, published 09/2004
|
-- |
05/2006 |
| 1.206 |
Combined License Applications for Nuclear Power Plants (LWR Edition)
- DG-1145, Proposed Revision 0, published 09/2006
|
-- |
06/2007 |
| 1.207 |
Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors |
-- |
03/2007 |
| 1.208 |
A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion |
-- |
03/2007 |
| 1.209 |
Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants
- DG-1142, Second Proposed Revision 0, published 10/2006
- Staff's responses to public comments on DG-1142
- DG-1077, "Guidelines for Environmental Qualification of Microprocessor-Based Equipment Important to Safety in Nuclear Power Plants," First Proposed Revision 0, published 09/2001
|
-- |
03/2007 |
| 1.210 |
Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants |
-- |
06/2008 |
| 1.211 |
Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants |
-- |
04/2009 |
1.212 |
Sizing of Large Lead-Acid Storage Batteries |
-- |
11/2008 |
| 1.213 |
Qualification of Safety-Related Motor Control Centers for Nuclear Power Plants |
-- |
05/2009 |
