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NRC Regulatory Guides - Power Reactors (Division 1)

This page lists the title, date issued, revisions, and some ADAMS accession numbers (ML) for each regulatory guide in Division 1, Power Reactors. A guide available at this site has an underscored number.

See also Draft Regulatory Guides for Division 1.

See Notes on Regulatory Guides for more information.

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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) (ML003739925) -- 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1.2 (Withdrawn -- See 56 FR 36175, 07/31/1991) -- --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 (Rev. 2, ML003739601) -- 11/1970
1 06/1973
2 06/1974
1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors (Rev. 2, ML003739614) -- 11/1970
1 06/1973
2 06/1974
1.5 Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) (ML003739923) -- 03/1971
1.6 Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6) (ML003739924) -- 03/1971
1.7

Control of Combustible Gas Concentrations in Containment (ML070290080) (Draft was issued as DG-1117, 08/2002, ML022210067) (Rev. 2, "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," was issued 11/1978, ML003739927) (Rev. 1 was issued 09/1976) (Rev. 0 was issued 03/1971)

-- 03/1971
1 09/1976
2 11/1978
3 03/2007
1.8 Qualification and Training of Personnel for Nuclear Power Plants (Draft RS 807-5, Proposed Revision 2, published 02/1979; Draft RS 807-5, Second Proposed Revision 2, published 09/1980; Draft OL 403-5, Third Proposed Revision 2, published 01/1985; Draft DG-1012, Proposed Revision 3, published 09/1996, DG-1084, Second Proposed Revision 3, published 03/1999) (Rev. 2, ML003739928; Rev. 3, ML003706932) -- 03/1971
1 09/1975
1-R 05/1977
2 04/1987
3 05/2000
1.9

Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants (Rev. 4, ML070380553) (Draft Rev. 4 was issued as DG-1172, 11/2006, ML062650307; see the staff's responses to public comments on DG-1172, ML070380364) (Rev. 3, "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants," was issued 07/1993, ML003739929) (Second Draft Rev. 3 was issued as DG-1021, 04/1992) (First Draft Rev. 3 was issued as RS 802-5, 11/1988) (Rev. 2 was issued 12/1979) (Rev. 1 was issued 11/1978) (Rev. 0 was issued 03/1971)

-- 03/1971
1 11/1978
2 12/1979
3 07/1993
4 03/2007
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 (ML003739934) -- 03/1971
1.12 Nuclear Power Plant Instrumentation for Earthquakes (Draft MS 140-5, Proposed Revision 2, published 07/1981) (DG-1016, the Second Proposed Revision 2, published 11/1992) (DG-1033, the Second Proposed Revision 2, published 02/1995) (Rev. 1, ML003739947; Rev. 2, ML003739944) -- 03/1971
1 04/1974
2 03/1997
1.13

Spent Fuel Storage Facility Design Basis (Rev. 2, ML070310035) (Second Draft Rev. 2 was issued as DG-1162, 10/2006, ML062680291; see the staff's responses to public comments on DG-1162, ML070300300) (First Draft Rev. 2 was issued as CE 913-5, 12/1981) (Rev. 1 was issued for comment 12/1975, ML003739943) (Rev. 0 was issued 03/1971)

-- 03/1971
1 12/1975
2 03/2007
1.14 Reactor Coolant Pump Flywheel Integrity (Rev. 1, ML003739936) -- 10/1971
1 08/1975
1.15 (Withdrawn -- See 46 FR 37579, 07/21/1981) -- --
1.16 Reporting of Operating Information -- Appendix A Technical Specifications (for Comment) (Rev. 4, ML003739954) -- 10/1971
1 10/1973
2 09/1974
3 01/1975
4 08/1975
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 (Rev. 3, ML070260376) (Draft Rev. 3 was issued as DG-1163, 11/2006, ML062750162; see the staff's responses to public comments on DG-1163, ML070260382) (Rev. 2 was issued 05/1976, ML003739957) (Rev. 1 was issued 06/1975) (Rev. 0 was issued 12/1971) -- 12/1971
1 06/1975
2 05/1976
3 03/2007
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 (Rev. 1, ML003739960) -- 12/1971
1 06/1974
1.22 Periodic Testing of Protection System Actuation Functions (Safety Guide 22) -- 02/1972
1.23

Meteorological Monitoring Programs for Nuclear Power Plants (Rev. 1, ML070350028) (Third Proposed Rev. 1 was issued as DG-1164, ML062540408, 10/2006; see the staff's responses to public comments on DG-1164, ML070360736) (Second Proposed Rev. 1, "Meteorological Measurement Program for Nuclear Power Plants," was issued as Draft ES 926-4, 04/1986, ML003739962) (First Proposed Rev. 1, "Meteorological Programs In Support of Nuclear Power Plants," was issued as Draft SS 926-4, 09/1980, ML060730055) (Rev. 0, "Onsite Meteorological Programs," was issued as Safety Guide 23, 02/1972, ML020360030)

-- 02/1972
1 03/2007
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 (Rev. 4, ML070290283) (Draft Rev. 4 was issued as DG-1152, 11/2006, ML063100379; no comments were received) (Rev. 3 was issued for comment, 02/1976, ML003739964) (Rev. 2 was issued 06/1975) (Rev. 1 was issued 09/1974) (Rev. 0 was issued 03/1972)

-- 03/1972
1 09/1974
2 06/1975
3 02/1976
4 03/2007
1.27 Ultimate Heat Sink for Nuclear Power Plants (for Comment) (Rev. 2, ML003739969) -- 03/1972
1 03/1974
2 01/1976
1.28 Quality Assurance Program Requirements (Design and Construction) (Rev. 3, ML003739981) (Draft RS 002-5, Proposed Revision 3, published 03/1981) (Draft DG-1010, Proposed Revision 4, published 11/1992) -- 06/1972
1 03/1978
2 02/1979
3 08/1985
1.29 Seismic Design Classification (Rev. 4, ML070310052) (Draft Rev. 4 was issued as DG-1156, 10/2006, ML062540294; see the staff's responses to public comments on DG-1156, ML070300537) (Rev. 3 was issued 09/1978, ML003739983) (Rev. 2 was issued 02/1976) (Rev. 1 was issued 08/1973) (Rev. 0 was issued 06/1972) -- 06/1972
1 08/1973
2 02/1976
3 09/1978
4 03/2007
1.30 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) (ML081270243) -- 08/1972
1.31 Control of Ferrite Content in Stainless Steel Weld Metal (Rev. 3, ML003739986) -- 08/1972
1 06/1973
2 05/1977
3 04/1978
1.32 Criteria for Power Systems for Nuclear Power Plants (Rev. 2, ML003739990) (DG-1079, Proposed Revision 3, issued 04/2003, ML031280598) (Rev. 3, ML040680488) -- 08/1972
1 03/1976
2 02/1977
3 03/2004
1.33 Quality Assurance Program Requirements (Operation) (Draft RS 902-4, Proposed Revision 3, published 08/1979) (Draft RS 902-4, Second Proposed Revision 3, published 11/1980) (Rev. 2, ML003739995) -- 11/1972
1 02/1977
2 02/1978
1.34 Control of Electroslag Weld Properties (ML003739997) -- 12/1972
1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Rev. 2, ML003740001) (Draft SC 810-4, Proposed Revision 3, published 04/1979) (Rev. 3, ML003740007) -- 02/1973
1 06/1974
2 01/1976
3 07/1990
1.35.1 Determining Prestressing Forces for Inspection of Prestressed Concrete Containments (ML003740040) (Draft SC 807-4 published 04/1979) -- 07/1990
1.36 Nonmetallic Thermal Insulation for Austenitic Stainless Steel (ML003740046) -- 02/1973
1.37

Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants (Rev. 1, ML070250571) (Draft Rev. 1, was issued as DG-1165, 10/2006, ML063040652; see the staff's responses to public comments on DG-1165, ML070300798) (Rev. 0 was issued 03/1973, ML003740051)

-- 03/1973
1 03/2007
1.38 Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants (Rev. 2, ML003740057) -- 03/1973
1 10/1976
2 05/1977
1.39 Housekeeping Requirements for Water-Cooled Nuclear Power Plants (Rev. 2, ML003740067) -- 03/1973
1 10/1976
2 09/1977
1.40 Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants (ML003740083) -- 03/1973
1.41 Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments (ML003740090) -- 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 (ML003740095) -- 05/1973
1.44 Control of the Use of Sensitized Stainless Steel (ML003740109) -- 05/1973
1.45

Guidance on Monitoring and Responding to Reactor Coolant System Leakage (Rev. 1, ML073200271)
(Rev. 0, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"  was issued 05/1973 ML003740113)

-- 05/1973
1 05/2008
1.46 (Withdrawn -- See 50 FR 9732, 03/11/1985) -- --
1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems (ML003740127) -- 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 (ML003740136) -- 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 (Rev. 2, ML003740139) (DG-1102, Proposed Revision 3, issued 10/00, ML003756180) (Rev. 3, ML011710176) -- 06/1973
1 07/1976
2 03/1978
3 06/2001
1.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems (ML003740182) (Draft DG-1118, Proposed Revision 1, ML021260080, published 05/2002) (Rev.1, ML032670945) (Rev. 2, ML033220006) -- 06/1973
1 10/2003
2 11/2003
1.54 Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants (ML003740187) (Draft DG-1976, Proposed Revision 1, ML003739156, published 03/1999) (Rev. 1, ML003714475) -- 06/1973
1 07/2000
1.55 (Withdrawn -- See 46 FR 37579, 07/21/1981) -- --
1.56 Maintenance of Water Purity in Boiling Water Reactors (for Comment) (Rev. 1, ML003740192) -- 06/1973
1 07/1978
1.57

Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components (Rev. 1, ML070310029) (Draft Rev. 1 was issued as DG-1158, 10/2006, ML063000278; see the staff's responses to public comments on DG-1158, ML070240173) (Rev. 0 was issued 06/1973, ML003740195)

-- 06/1973
1 03/2007
1.58 (Withdrawn -- See 56 FR 36175, 07/31/1991) -- --
1.59 Design Basis Floods for Nuclear Power Plants (Errata published 07/30/1980) (Rev. 2, ML003740388) -- 08/1973
1 04/1976
2 08/1977
1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants (Rev. 1, ML003740207) -- 10/1973
1 12/1973
1.61

Damping Values for Seismic Design of Nuclear Power Plants (Rev. 1, ML070260029) (Draft Rev. 1 was issued as DG-1157, 10/2006, ML062680189; see the staff's responses to public comments on DG-1157, ML070310420) (Rev. 0 was issued 10/1973, ML003740213)

-- 10/1973
1 03/2007
1.62 Manual Initiation of Protective Actions (ML003740216) -- 10/1973
1.63 Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants (Draft EE 405-4, Proposed Revision 3, published 06/1986) (Rev. 3, ML003740219) -- 10/1973
1 05/1977
2 07/1978
3 02/1987
1.64 (Withdrawn -- See 56 FR 36175, 07/31/1991) -- --
1.65 Materials and Inspections for Reactor Vessel Closure Studs (ML003740228) -- 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 (Rev. 3, ML070260039) (Draft Rev. 3 was issued as DG-1166, 11/2006, ML062750316; see the staff's responses to public comments on DG-1166, ML070360680) (Rev. 2 was issued 08/1978) (Rev. 1 was issued 01/1977) (Rev. 0 was issued 11/1973) -- 11/1973
1 01/1977
2 08/1978
3 03/2007
1.68.1 Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants (Rev. 1, ML003740230) -- 12/1975
1 01/1977
1.68.2 Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants (Rev. 1, ML003740258) -- 01/1977
1 07/1978
1.68.3 Preoperational Testing of Instrument and Control Air Systems (Draft RS 709-4, a proposed revision to Regulatory Guide 1.80, published 10/1980) (ML003740231) -- 04/1982
1.69 Concrete Radiation Shields for Nuclear Power Plants (ML003740235) -- 12/1973
1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) (Rev. 2, ML010610289) (Rev. 3 in three parts, ML011340072, ML011340108, and ML011340116) -- 02/1972
1 10/1972
2 09/1975
3 11/1978
1.71

Welder Qualification for Areas of Limited Accessibility (Rev. 1, ML070320476) (Draft Rev. 1 was issued as DG-1167, 10/2006, ML062840416; see the staff's responses to public comments on DG-1167, ML070330481) (Rev. 0 was issued 12/1973, ML003740244)

-- 12/1973
1 03/2007
1.72

Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin (Rev. 2, ML003740253) -- 12/1973
1 01/1978
2 11/1978
1.73 Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants (ML003740261) -- 01/1974
1.74 (Withdrawn -- See 54 FR 38919, 09/21/1989) -- --
1.75 Physical Independence of Electric Systems (Rev. 2, ML003740265) (Rev. 3, ML043630448) -- 02/1974
1 01/1975
2 09/1978
3 02/2005
1.76 Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants (Rev. 1, ML070360253) (Draft Rev. 1 was issued as DG-1143, 01/2006, ML053140225; see the staff's responses to public comments on DG-1143, ML070360258) (Rev. 0, "Design-Basis Tornado for Nuclear Power Plants," was issued 04/1974, ML003740273) -- 04/1974
1 03/2007
1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors (ML003740279) -- 05/1974
1.78 Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release (ML003740298) (Proposed Revision 1, DG-1087, published 02/2001, ML010440064) (Revision 1 incorporates guidance from withdrawn Regulatory Guide 1.95) (Revision 1, ML013100014) -- 06/1974
1 12/2001
1.79 Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors (Rev. 1, ML003740351) -- 06/1974
1 09/1975
1.80 (Withdrawn -- See 47 FR 19258, 05/4/1982) Reissued as Regulatory Guide 1.68.3, a renumbered revision to this guide with an expanded scope that addresses control air systems. -- --
1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants (Rev. 1, ML003740343) -- 06/1974
1 01/1975
1.82 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident (Draft MS 203-4, Proposed Revision 1, published 05/1983) (Rev. 1, ML003740236) (Draft DG-1038, Proposed Revision 2, ML003739202, published 07/1995) (Rev. 2, ML003740249) (Rev. 3, ML033140347)
-- 06/1974
1 11/1985
2 05/1996
3 11/2003
1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes (Rev. 1, ML003740256) -- 06/1974
1 07/1975
1.84

Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
Design, Fabrication, and Materials Code Case Acceptability, ASME Section III Because this guide is frequently revised, only the current revision and date are listed in the appropriate columns. Previous revisions and their publication dates are as follows: 0, 06/1974; 1, 04/1975; 2, 06/1975; 3, 09/1975; 4, 11/1975; 5, 03/1976; 6, 05/1976; 7, 08/1976; 9, 03/1977; 10, 08/1977; 11, 11/1977; 12, 03/1978; 13, 07/1978; 14, 11/1978; 15, 05/1979; 16, 05/1980; 17, 12/1980; 18, 08/1981; 19, 04/1982; 20, 11/1982; 21, 09/1983; 22, 07/1984; 23, 09/1985; 24, 06/1986; 25, 05/1988; 26 (ML003740266), 07/1989; 27, 11/1990; 28, 04/1992; 29, 07/1993; 30 (ML003740275), 10/1994; proposed 31 (DG-1049, ML003739376), 05/1997; 31 (ML003740283), 05/1997; proposed Rev. 32 of RGs 1.84 and 1.85 combined (DG-1090, ML013120011), 12/2001; 32(RGs 1.84 and 1.85 combined, ML030730417), 06/2003; proposed 33 (DG-1124, ML040850299), 04/2004; 33 (ML052130562), 08/2005; 34 (ML072070407), 10/2007

33 08/2005
34 10/2007
1.85 (Withdrawn 06/2003) Materials Code Case Acceptability -- ASME Section III, Division 1 (Guidance incorporated into Revision 32 of Regulatory Guide 1.84, published 06/2003, ML041620482) 31 05/1999
1.86
Termination of Operating Licenses for Nuclear Reactors (ML003740243) -- 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) (Rev. 1, ML003740252) -- 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 (1974, ML012880422) (Draft EE 042-2, Proposed Revision 1, published 02/1982) (Rev. 1, ML003740271) -- 11/1974
1 06/1984
1.90 Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons (Rev. 1, ML003740281) -- 11/1974
1 08/1977
1.91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants (Rev. 1, ML003740286) -- 01/1975
1 02/1978
1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis (Rev. 0, 12/1974) (Rev. 1, ML003740290, 02/1976) (Proposed Revision 2, published as DG-1108, 08/2001) (Second Proposed Revision 2, published as DG-1127, ML050230006, 02/2005) (Rev.2, ML053250475, 07/2006) -- 12/1974
1 02/1976
2 07/2006
1.93 Availability of Electric Power Sources (ML003740292) -- 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 (Rev. 1, ML003740305) (Draft RS 908-5, Proposed Revision 2, published 09/1979) -- 04/1975
1 04/1976
1.95 (Withdrawn January 2002) Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release (Rev. 1, ML003740310) (Guidance incorporated into Revision 1 of Regulatory Guide 1.78, published 01/2002) (Withdrawn 12/26/2001, ML020020470) -- --
1.96 Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants (Rev. 1, ML003740263) -- 05/1975
1 06/1976
1.97 Criteria For Accident Monitoring Instrumentation For Nuclear Power Plants (Rev. 0, entitled "Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident," 12/1975) (Rev. 1, 08/1977) (Proposed Rev. 2, Draft RS 917-4, 12/1979) (Rev. 2, ML060750525, 12/1980) (Rev. 2 Errata, ML060750527, 07/1981) (Rev. 3, ML003740282, 05/1983) (Proposed Rev. 4, DG-1128, ML052150210, 08/2005) (Rev.4, ML061580448, 06/2006) -- 12/1975
1 08/1977
2 12/1980
3 05/1983
4 06/2006
1.98 Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment) (ML003740259) -- 03/1976
1.99 Radiation Embrittlement of Reactor Vessel Materials (Draft ME 305-4, Proposed Revision 2, published 02/1986) (Rev. 2, ML003740284) -- 07/1975
1 04/1977
2 05/1988
1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants (Draft EE 108-5, Proposed Revision 2, published 08/1987) (Rev. 2, ML003740293) -- 03/1976
1 08/1977
2 06/1988

1.101

Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 to this guide, "Emergency Planning for Nuclear Power Plants," was withdrawn--see 45 FR 69610, 10/21/1980.) (Draft DG-1022, Proposed Revision 3, published 02/1992) (Rev. 3, ML003740302) (Draft DG-1075, Proposed Revision 4, published 03/2000, ML003687957) (Rev. 4, ML032020276) (Rev. 5, ML050730286) -- 11/1975
1 03/1977
2 10/1981
3 08/1992
4 07/2003
5 06/2005
1.102 Flood Protection for Nuclear Power Plants (ML003740308) -- 10/1975
1 09/1976
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 (Draft IC 010-5, Proposed Revision 2, published 12/81) (Draft DG-1045, Proposed Revision 3, ML003739248, published 10/96) (Rev. 2, ML003740318; Rev. 3, ML993560062) -- 11/1975
1 11/1976
2 02/1986
3 12/1999
1.106 Thermal Overload Protection for Electric Motors on Motor-Operated Valves (Rev. 1, ML003740323) -- 11/1975
1 03/1977
1.107 Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures (Rev. 1, ML003740374) -- 11/1975
1 02/1977
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
(2.71 MB)
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 (Rev. 1, ML003740384) -- 03/1976
1 10/1977
1.110 Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (for Comment) (ML003740332) -- 03/1976
1.111
(1.25 MB)
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors (Rev. 1, ML003740354) -- 03/1976
1 07/1977
1.112
Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors (Rev. 1, ML070320241) (Draft Rev. 1, was issued as DG-1160, 10/2006, ML062680253; see the staff's responses to public comments on DG-1160, ML070360671) (Rev. 0-R was issued as errata, 05/1977, ML003740361) (Rev. 0 was issued 04/1976) -- 04/1976
0-R 05/1977
1 03/2007
1.113
(2.18 MB)
Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I (Rev. 1, ML003740390) -- 05/1976
1 04/1977
1.114 Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit (Draft HF 601-4, Proposed Revision 2, published 12/1986) (Rev. 2, ML003740393) -- 02/1976
1 11/1976
2 05/1989
1.115 Protection Against Low-Trajectory Turbine Missiles (Rev. 1, ML003739456) -- 03/1976
1 07/1977
1.116 Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems (Rev. 0-R, ML003739465) -- 06/1976
0-R 05/1977
1.117 Tornado Design Classification (Rev. 1, ML003739346) -- 06/1976
1 04/1978
1.118 Periodic Testing of Electric Power and Protection Systems (Rev. 3, ML003739468) (DG-1028, Proposed Revision 3, published 09/1994) (Rev. 3, ML003739468) -- 06/1976
1 11/1977
2 06/1978
3 04/1995
1.119 (Withdrawn -- See 42 FR 33387, 06/30/1977) -- --
1.120

Withdrawn August 15, 2001 (Fire Protection Guidelines for Nuclear Power Plants) (issued 06/1976, Revision 1 issued 11/1977) (Rev. 1 ML003739360, Withdrawal ML012340082) -- --
--
--
1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (for Comment) (ML003739366) -- 08/1976
1.122

Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components (Rev. 1, ML003739367) -- 09/1976
1 02/1978
1.123 (Withdrawn -- See 56 FR 36175, 07/31/1991) -- --
1.124

Service Limits and Loading Combinations for Class 1 Linear-Type Supports (Rev. 2, ML070160591) (Draft Rev. 2, was issued as DG-1168, "Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports," 10/2006, ML063000449; see the staff's responses to public comments on DG-1168, ML070160604) (Rev. 1 was issued 01/1978, ML003739380) (Rev. 0 was issued 11/1978).

-- 11/1976
1 01/1978
2 02/2007
1.125 Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants (Rev. 1, ML003739388) -- 03/1977
1 10/1978
1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification (Rev. 1, ML003739385) -- 03/1977
1 03/1978
1.127 Inspection of Water-Control Structures Associated with Nuclear Power Plants (Rev. 1, ML003739392) -- 04/1977
1 03/1978
1.128 Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Rev. 2, ML070080013) (Draft Rev. 2, was issued as DG-1154, 10/2006, ML062220170; see the staff's responses to public comments on DG-1154, ML070030154) (Rev. 1, "Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants," was issued 10/1978, ML003740099) (Rev. 0 was issued 04/1977) -- 04/1977
1 10/1978
2 02/2007
1.129 Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Rev. 2, ML063490110) (Draft Rev. 2, was issued as DG-1155, 10/2006, ML062540343; see the staff's responses to public comments on DG-1155, ML063490093) (Rev. 1, "Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," was issued 02/1978, ML003740104) (Rev. 0 was issued 04/1977) -- 04/1977
1 02/1978
2 02/2007
1.130

Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports (Rev. 2, ML070170053) (Draft Rev. 2 was issued as DG-1169, 10/2006, ML063000484; see the staff's responses to public comments on DG-1169, ML070170058) (Rev. 1 was issued 10/1978, ML003740123) (Rev. 0 was issued 07/1977)

-- 07/1977
1 10/1978
2 03/2007
1.131 Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (for Comment) (ML003740128) -- 08/1977
1.132 Site Investigations for Foundations of Nuclear Power Plants (Rev. 2, ML032800710) (DG-1101, Proposed Revision 2, issued 02/2001, ML010510162) (Rev. 1, ML003740350) -- 09/1977
1 03/1979
2 10/2003
1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Rev. 1, ML003740137) -- 09/1977
1 05/1981
1.134 Medical Evaluation of Licensed Personnel at Nuclear Power Plants (Draft OL 401-5, Proposed Revision 2, published 11/1984) (Draft DG-1068, Proposed Revision 3, ML003739137, published 02/1997) (Rev. 2, ML003740138) (Rev. 3, ML003740140) -- 09/1977
1 03/1979
2 04/1987
3 03/1998
1.135 Normal Water Level and Discharge at Nuclear Power Plants (for Comment) (ML003740143) -- 09/1977
1.136 Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments (Rev. 3, ML070310045) (Draft Rev. 3 was issued as DG-1159, 10/2006, ML063000430; see the staff's responses to public comments on DG-1159, ML070240146) (Rev. 2, "Materials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through -6000 of the 'Code for Concrete Reactor Vessels and Containments')," was issued 06/1981, ML003740155) (Draft Rev. 2 was issued as SC 814-5, 11/1979) (Rev. 1 was issued 10/1978) (Rev. 0 was issued 11/1977) -- 11/1977
1 10/1978
2 06/1981
3 03/2007
1.137 Fuel-Oil Systems for Standby Diesel Generators (Rev. 1, ML003740180) -- 01/1978
1 10/1979
1.138 Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants (04/1978, ML003740184) (DG-1109, Proposed Revision 1, published 08/2001, ML012420328) (Revision 1 was not published) (Revision 2, ML033510166) -- 04/1978
1 --
2 12/2003
1.139

(Withdrawn -- See 73 FR 32750, 06/10/2008)

-- --
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) (Rev. 1, ML003740190; Rev. 2, ML011710150) -- 03/1978
1 10/1979
2 06/2001
1.141 Containment Isolation Provisions for Fluid Systems (for Comment) (ML003740194) -- 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) (Rev. 1, ML003740197; Rev. 2, ML013100274) -- 04/1978
1 10/1981
2 11/2001
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) (Rev. 1, ML003740200; Rev. 2, ML013100305) -- 07/1978
1 10/1979
2 11/2001
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) (Rev. 1, ML003740205) -- 08/1979
1 11/1982
1.146 (Withdrawn -- See 56 FR 36175, 07/31/1991) -- --
1.147

Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1
Because this guide is frequently revised, only the current revision and date are listed in the appropriate columns. Previous revisions and their publication dates are as follows: Draft SC 721-4, 08/1979; 0, 03/1981; 2, 06/1983; 3, 07/1984; 4, 09/1985; 5, 08/1986; 6, 05/1988; 7 (ML003740209), 07/1989; 8, 11/1990; 9, 04/1992; 10, 07/1993; 11 (ML003739955), 10/1994; proposed 12 (DG-1050, ML003739242), 05/1997; 12 (ML003671361), 05/1999; proposed 13 (DG-1091, ML013120019), 12/2001; 13 (ML030730423), 06/2003; corrected reprint of Rev. 13 (ML040230509), 01/2004; proposed 14 (DG-1125, ML040850346), 08/2004; 14 (ML052510117), 08/2005; 15 (ML072070419), 10/2007

14 08/2005
15 10/2007
1.148 Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants (ML003739979) (Draft SC 704-5 published 02/1979) -- 03/1981
1.149 Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations (Draft RS 110-5 published 07/1980) (Draft OL 402-5, Proposed Revision 1, published 11/1984) (Draft DG-1043, Proposed Revision 2, published 06/1995) (DG-1080, Proposed Revision 3, ML003739149, published 08/1999) (Rev. 1, ML003739984; Rev. 2, ML003739988; Rev. 3, ML012770164) -- 04/1981
1 04/1987
2 04/1996
3 10/2001
1.150 (Withdrawn-- See 73 FR 7766, 02/11/2008)  -- --
1.151 Instrument Sensing Lines (ML003740003) (Draft IC 126-5 published 03/1982) -- 07/1983
1.152 Criteria for Digital Computers in Safety Systems of Nuclear Power Plants (11/85) (ML003740088) (Draft IC 127-5 published 03/1983) (Draft DG-1039, Proposed Revision 1, published 05/1995) (Rev. 1, ML003740015) (Draft DG-1130, Proposed Revision 2, Published 12/2004) (Rev. 2, ML053070150) -- 11/1985
1 01/1996
2 01/2006
1.153 Criteria for Safety Systems (12/85) (Draft IC 609-5 published 12/1982) (Draft DG-1042, Proposed Revision 1, published 11/1995) (ML003740019) (Rev. 1, ML003740022)
-- 12/1985
1 06/1996
1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors (ML003740028) (Draft SI 502-4 published 01/1986) -- 01/1987
1.155 Station Blackout (Issued June 1988, reissued August 1988 with corrected tables) (ML003740034) (Draft SI 501-4 published 03/1986) -- 08/1988
1.156 Environmental Qualification of Connection Assemblies for Nuclear Power Plants (ML003740042) (Draft EE 404-4 published 05/1987) -- 11/1987
1.157 Best-Estimate Calculations of Emergency Core Cooling System Performance (ML003739584) (Draft RS 701-4 published 03/1987) -- 05/1989
1.158 Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants (ML003740047) (Draft EE 006-5 published 08/1987) -- 02/1989
1.159 Assuring the Availability of Funds for Decommissioning Nuclear Reactors (Draft DG-1003 published 05/1989, ML003739365) (Draft DG-1106, Proposed Revision 1, published 05/2001, ML010170350) (08/90, ML003740066) (Rev. 1, ML032790365) -- 08/1990
1 10/2003
1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Draft DG-1020 published 11/1992) (Draft DG-1031, Proposed Revision 1, published 06/1994) (Draft DG-1051, Proposed Revision 2, ML003739233, published 08/1996) (Rev. 1, ML031430362) (Rev. 2, ML003761662) -- 06/1993
1 01/1995
2 03/1997
1.161 Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb (ML003740038) (Draft DG-1023 published 09/1993) -- 06/1995
1.162 Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels (ML003740052) (Draft DG-1027 published 10/1994) -- 02/1996
1.163 Performance-Based Containment Leak-Test Program (ML003740058) (Draft DG-1037 published 02/1995) (Errata to NEI 94-01 published 03/1996) -- 09/1995
1.164 (Not yet issued)    
1.165 Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion (ML003740084) (Draft DG-1015 issued 11/1992, Draft DG-1032, issued 02/1995) -- 03/1997
1.166 Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions (ML003740089) (Draft DG-1017 issued 11/1992, Draft DG-1034, ML003739203, issued 02/1995) -- 03/1997
1.167 Restart of a Nuclear Power Plant Shut Down by a Seismic Event (ML003740093) (Draft DG-1018 issued 11/1992, Draft DG-1035, ML003739196, issued 02/1995) -- 03/1997
1.168 Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (DG-1054, ML003739159, issued 08/1996) (09/97, ML003740098) (DG-1123, Proposed Revision 1, 01/2003, ML030270328) (Rev. 1, ML040410189) -- 09/1997
1 02/2004
1.169 Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (ML003740102) (Draft DG-1055, ML003739153, issued 08/1996) -- 09/1997
1.170 Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (ML003740105) (Draft DG-1056, ML003739146, issued 08/1996) -- 09/1997
1.171 Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (ML003740108) (Draft DG-1057, ML003739141, issued 08/1996) -- 09/1997
1.172 Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (ML003740094) (Draft DG-1058, ML003739228, issued 08/1996) -- 09/1997
1.173 Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (ML003740101) (Draft DG-1059, ML003740101, issued 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 (ML003740133) (Issued with SRP Chapter 19) (Draft DG-1061, ML003739197, issued 06/1997) (Draft DG-1110, Proposed Revision 1, issued 06/2001) (Revision 1, issued 11/2002, ML023240437) -- 07/1998
1 11/2002
1.175 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (ML003740149) (Issued with SRP Chapter 3.9.7) (Draft DG-1062, ML003739158, issued 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 (ML003740176) (Issued with SRP Chapter 16.1) (Draft DG-1065, ML003739150, issued 06/1997) -- 08/1998
1.178 An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping (9/98, ML003740181) (Issued with SRP Chapter 3.9.8 ) (Draft DG-1063, ML003739154, issued 10/1997) (Revision 1, ML032510128, issued 09/2003) (SRP, ML032510135) -- 09/1998
1 09/2003
1.179 Standard Format and Content of License Termination Plans for Nuclear Power Reactors (ML003740212) (Draft DG-1078, ML003739152, issued 04/1998) -- 01/1999
1.180
Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems (01/00, ML003740218) (Draft DG-1029 published 02/1998, ML003739326) (Rev. 1, ML032740277) (DG-1119, proposed Revision 1, ML022390236, published 08/2002) -- 01/2000
1 10/2003
1.181
Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) (ML003740112) (Draft DG-1083 issued 03/1999) -- 09/1999
1.182 Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants (ML003740117) (Draft DG-1082 issued 12/1999) -- 05/2000
1.183 Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (ML003716792) (Draft DG-1081, ML993490086, issued 12/1999) -- 07/2000
1.184 Decommissioning of Nuclear Power Reactors (ML003701137) (Draft DG-1067, ML003739144, issued 06/1997) (Errata to update Reference 1 (ML040920341), published 04/2004) -- 07/2000
1.185 Standard Format and Content for Post-Shutdown Decommissioning Activities Report (ML003701163) (Draft DG-1071, ML003739227, issued 12/1997) (Errata to update Reference 1 (ML040920341), published 04/2004) -- 07/2000
1.186 Guidance and Examples for Identifying 10 CFR 50.2 Design Bases (ML003754825) (Draft DG-1093, ML003691412, published 04/2000) -- 12/2000
1.187 Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments (ML003759710) (Draft DG-1095, ML003698165, issued 04/2000) -- 11/2000
1.188
Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses (ML012010322) (Drafts were issued as DG-1104, ML003736097, 08/2000; DG-1047, ML003739244, 08/1996; and DG-1009, 12/1990.) (Proposed Rev. 1 was issued as DG-1140, ML050230010, 01/2005.) (Rev. 1, ML051920430, 09/2005.) -- 07/2001
1 09/2005
1.189

Fire Protection for Nuclear Power Plants (Rev. 1, ML070370183) (Draft Rev. 1 was issued as DG-1170, 11/2006, ML063100359; see the staff's responses to public comments on DG-1170, DG-1097, and DG-1094, ML070320468) (Rev. 0, "Fire Protection for Operating Nuclear Power Plants," was issued 04/2001, ML010920084) (Second Draft Rev. 0 was issued as DG-1097, 06/2000, ML003711848) (First Draft Rev. 0 was issued as DG-1094, 10/1999, ML993140328)

-- 04/2001
01 03/2007
1.190 Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence (ML010890301) (Drafts were DG-1053 and DG-1025 (09/1993)) (DG-1025, ML003739334) -- 03/2001
1.191 Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown (ML011500010) (Draft DG-1069, ML003739129, published 07/1998) -- 05/2001
1.192 Operation and Maintenance Code Case Acceptability, ASME OM Code (ML030730430) (Draft guide was issued as DG-1089, 12/01, ML013120051) -- 06/2003
1.193

ASME Code Cases Not Approved for Use (Original draft guide was issued as DG-1112, ML013120071, 12/2001) (Rev. 0, ML030730440, 06/2003) (proposed Rev. 1, DG-1126, ML040850236, 08/2004) (Rev. 1, ML052140501, 08/2005) (Rev. 2, ML072470294), 10/2007

-- 06/2003
1 08/2005
2 10/2007
1.194 Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants (ML031530505) (Draft guide was issued as DG-1111, 12/01, ML013130132) -- 06/2003
1.195 Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors (ML031490640) (Draft guide was issued as DG-1113, 01/02, ML020160023) -- 05/2003
1.196

Control Room Habitability at Light-Water Nuclear Power Reactors (ML063560144) (Rev. 0 was issued 05/2003, ML031490611) (Draft Rev. 0 was issued as DG-1114, 03/02, ML020790125)

-- 05/2003
1 01/2007
1.197 Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors (ML031490664) (Draft guide was issued as DG-1115, 03/02, ML020790191) -- 05/2003
1.198 Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites (ML033280143) (Draft guide was issued as DG-1105, 03/01, ML010650295) -- 11/2003
1.199 Anchoring Components and Structural Supports in Concrete (ML033360660) (Draft was issued as DG-1099, 07/02, ML021910490) -- 11/2003
1.200

An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities, ML070240001 (Clarification to RG 1.200, Rev. 1, ML071940235) (Draft Rev. 1 was issued as DG-1161, 09/2006, ML062480134) (Rev. 0, 02/2004, ML040630078, was issued with SRP Chapter 19.1, ML040630300) (Draft Rev. 0 was issued as DG-1122, 11/02, ML023360076)

-- 02/2004
1 01/2007
1.201 Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance (Rev. 0, ML060260164) (Draft guide was issued as DG-1121, 05/03, ML031430373) (Rev. 1, ML061090627, 05/2006) -- 01/2006
1 05/2006
1.202 Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors (ML050230008) (Draft guide was issued as DG-1085, 11/2001, ML013100099) -- 02/2005
1.203 Transient and Accident Analysis Methods (ML053500170) (Issued with ML053550265) SRP Section 15.0.2 , ML053550265, 12/2005) (Drafts were issued as DG-1096, ML003770849, 12/2000, and DG-1120, ML030160652, 12/2002) -- 12/2005
1.204 Guidelines for Lightning Protection of Nuclear Power Plants (ML052290422) (Draft guide was issued as DG-1137, 02/ 2005, ML050480101) -- 11/2005
1.205 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants (ML061100174) (Draft was issued as DG-1139, ML042740308, dated September 2004) -- 05/2006
1.206 Combined License Applications for Nuclear Power Plants (LWR Edition). Publication of the associated revision to Title 10 Code of Federal Regulations Part 52 is pending. (Draft guide was issued as DG-1145, dated September 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 (Rev. 0, ML070380586)
(Draft was issued as DG-1144, 07/2006, ML060970173; see the staff's responses to public comments on DG-1144, ML070510687)
-- 03/2007
1.208 A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion (Rev. 0, ML070310619) (Draft was issued as DG-1146, 10/2006, ML063030291; see the staff's responses to public comments on DG-1146, ML070380437)
-- 03/2007
1.209 Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants (Rev. 0, ML070190294) (Second Draft was issued as DG-1142, 10/2006, ML063040591; see the staff's responses to public comments on DG-1142, ML070260193) (First Draft was issued as DG-1077, "Guidelines for Environmental Qualification of Microprocessor-Based Equipment Important to Safety in Nuclear Power Plants," dated September 2001, ML012710073)
-- 03/2007
1.210

Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants (ML080640184)

-- 06/2008


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