Division 1 -- Power Reactors

 

Guide
Number

Title

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(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.3

Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors

06/1974

1.4

Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors

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)

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 Following a Loss-of-Coolant Accident

11/1978

1.8

Qualification and Training of Personnel for Nuclear Power Plants (Draft RS 807-5, Proposed Revision 2, published 2/1979; Draft RS 807-5,
Second Proposed Revision 2, published 9/1980; Draft OL 403-5,
Third Proposed Revision 2, published 1/1985; Draft DG-1012, Proposed Revision 3, published 9/1996)

04/1987

1.9

Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants (Draft RS 802-5, Proposed Revision 3, published 11/1988) (Draft DG-1021,Second Proposed Revision 3, published 4/1992)

07/1993

1.10

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.11

Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) Supplement to Safety Guide 11, Backfitting Considerations

02/1972

1.12

Nuclear Power Plant Instrumentation for Earthquakes (Draft MS 140-5,Proposed Revision 2, published 7/1981) (DG-1016, the Second Proposed Revision 2, published 11/1992) (DG-1033, the Second Proposed Revision 2, published 2/1995)

03/1997

1.13

Spent Fuel Storage Facility Design Basis (for Comment) (Draft CE 913-5, Proposed Revision 2, published 12/1981)

12/1975

1.14

Reactor Coolant Pump Flywheel Integrity (for Comment)

08/1975

1.15

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.16

Reporting of Operating Information--Appendix A Technical Specifications (for Comment)

08/1975

1.17

(Withdrawn--See 56 FR 30777, 7/5/1991)

--

1.18

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.19

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.20

Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing

05/1976

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

06/1974

1.22

Periodic Testing of Protection System Actuation Functions (Safety Guide 22)

02/1972

1.23

Onsite Meteorological Programs (Safety Guide 23) (Draft SS 926-4, Proposed Revision 1, published 9/1980) (Draft ES 926-4, Second Proposed Revision 1, published 4/1986)

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 (for Comment)

02/1976

1.27

Ultimate Heat Sink for Nuclear Power Plants (for Comment)

01/1976

1.28

Quality Assurance Program Requirements (Design and Construction) (Draft RS 002-5, Proposed Revision 3, published 3/1981) (Draft DG-1010, Proposed Revision 4, published 11/1992)

08/1985

1.29

Seismic Design Classification

09/1978

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

04/1978

1.32

Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants

02/1977

1.33

Quality Assurance Program Requirements (Operation) (Draft RS 902-4, Proposed Revision 3, published 8/1979) (Draft RS 902-4, Second Proposed Revision 3, published 11/1980)

02/1978

1.34

Control of Electroslag Weld Properties

2/1972

1.35

Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Draft SC 810-4, Proposed Revision 3, published 4/1979)

07/1990

1.35.1

Determining Prestressing Forces for Inspection of Prestressed Concrete Containments (Draft SC 807-4 published 4/1979)

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

03/1973

1.38

Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants

05/1977

1.39

Housekeeping Requirements for Water-Cooled Nuclear Power Plants

09/1977

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, 3/22/1976)

--

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

Reactor Coolant Pressure Boundary Leakage Detection Systems

05/1973

1.46

(Withdrawn--See 50 FR 9732, 3/11/1985)

--

1.47

Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems

05/1973

1.48

(Withdrawn--See 50 FR 9732, 3/11/1985)

--

1.49

Power Levels of Nuclear Power Plants

12/1973

1.50

Control of Preheat Temperature for Welding of Low-Alloy Steel

05/1973

1.51

(Withdrawn--See 40 FR 30510, 7/21/1975)

--

1.52

Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants

03/1978

1.53

Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems

06/1973

1.54

Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants (Draft DG-1076, Proposed Revision 1, published March 1999)

06/1973

1.55

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.56

Maintenance of Water Purity in Boiling Water Reactors (for Comment)

07/1978

1.57

Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components

06/1973

1.58

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.59

Design Basis Floods for Nuclear Power Plants (Errata published 7/30/1980)

08/1977

1.60

Design Response Spectra for Seismic Design of Nuclear Power Plants

12/1973

1.61

Damping Values for Seismic Design of Nuclear Power Plants

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 6/1986)

02/1987

1.64

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

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, 4/27/1983)

--

1.68

Initial Test Programs for Water-Cooled Nuclear Power Plants

08/1978

1.68.1

Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants

01/1977

1.68.2

Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants

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)

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)  Part 1

11/1978

 

Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)  Part 2

 

 

Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) Part 3

 

1.71

Welder Qualification for Areas of Limited Accessibility

12/1973

1.72

Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin

11/1978

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, 9/21/1989)

--

1.75

Physical Independence of Electric Systems

09/1978

1.76

Design Basis Tornado for Nuclear Power Plants

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

12/2001

1.79

Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors

09/1975

1.80

(Withdrawn--See 47 FR 19258, 5/4/1982) 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

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 5/1983) (Draft DG-1038, Proposed Revision 2, published 7/1995)

05/1996

1.83

Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes

07/1975

1.84

Design and Fabrication Code Case Acceptability--ASME Section III, Division 1

05/1999

1.85

Materials Code Case Acceptability--ASME Section III, Division 1

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, 1 06/1975 and 1596)

06/1975

1.88

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.89

Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants (Draft EE 042-2, Proposed Revision 1, published 2/1982)

06/1984

1.90

Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons

08/1977

1.91

Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants

02/1978

1.92

Combining Modal Responses and Spatial Components in Seismic Response Analysis

02/1976

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 9/1979)

04/1976

1.95

Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release

01/1977

1.96

Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants

06/1976

1.97

Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident (Errata published 7/1981) (Draft RS 917-4, Proposed Revision 2, published 12/1979)

05/1983

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 2/1986)

05/1988

1.100

Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants (Draft EE 108-5, Proposed Revision 2, published 8/1987)

06/1988

1.101

Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 to this guide entitled "Emergency Planning for Nuclear Power Plants" was withdrawn--see 45 FR 69610, 10/21/1980.) (Draft DG-1022, Proposed Revision 3, published 2/1992)

08/1992

1.102

Flood Protection for Nuclear Power Plants

09/1976

1.103

(Withdrawn--See 46 FR 37579, 7/21/1981)

--

1.104

(Withdrawn--See 44 FR 49321, 8/22/1979) See NUREG-0554, "Single-Failure-Proof Cranes for Nuclear Power Plants."

--

1.105

Instrument Setpoints for Safety-Related Systems

12/1999

1.106

Thermal Overload Protection for Electric Motors on Motor-Operated Valves

03/1977

1.107

Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures

02/1977

1.108

(Withdrawn--See 58 FR 41813, 8/5/1993) (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

10/1977

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

07/1977

1.112

Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors

05/1977

1.113

Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I

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)

05/1989

1.115

Protection Against Low-Trajectory Turbine Missiles

07/1977

1.116

Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems

05/1977

1.117

Tornado Design Classification

04/1978

1.118

Periodic Testing of Electric Power and Protection Systems (DG-1028, Proposed Revision 3, published 9/1994)

04/1995

1.119

(Withdrawn--See 42 FR 33387, 6/30/1977)

--

1.120

Fire Protection Guidelines for Nuclear Power Plants (for Comment)

11/1977

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

02/1978

1.123

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.124

Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports

01/1978

1.125

Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants

10/1978

1.126

An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification

03/1978

1.127

Inspection of Water-Control Structures Associated with Nuclear Power Plants

03/1978

1.128

Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants

10/1978

1.129

Maintenance, Testing, and Replacemen t of Large Lead Storage Batteries for Nuclear Power Plants

02/1978

1.130

Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports

10/1978

1.131

Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (for Comment) (Draft RS 050-2, Proposed Revision 1, published 8/1979)

08/1977

1.132

Site Investigations for Foundations of Nuclear Power Plants

03/1979

1.133

Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors

05/1981

1.134

Medical Evaluation of Licensed Personnel for Nuclear Power Plants (Draft OL 401-5, Third Proposed Revision 2, published 11/1984) (Draft DG-1068, Proposed Revision 3, published 2/1997)

03/1998

1.135

Normal Water Level and Discharge at Nuclear Power Plants (for Comment)

09/1977

1.136

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)

06/1981

1.137

Fuel-Oil Systems for Standby Diesel Generators

10/1979

1.138

Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (for Comment)

04/1978

1.139

Guidance for Residual Heat Removal (for Comment)

05/1978

1.140

Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants

10/1979

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)

11/2001

1.143

Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants

11/2001

1.144

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.145

Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (Reissued 2/1983 to correct page 1.145-7)

11/1982

1.146

(Withdrawn--See 56 FR 36175, 7/31/1991)

--

1.147

Inservice Inspection Code Case Acceptability--ASME Section XI, Division 1

05/1999

1.148

Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants (Draft SC 704-5 published 2/1979)

03/1981

1.149

Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations (Draft RS 110-5 published 7/1980) (Draft OL 402-5, Proposed Revision 1, published 11/1984) (Draft DG-1043, Proposed Revision 2, published 6/1995) (Draft DG-1080, Proposed Revision 3 published 8/1999)

10/2001

1.150

Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations (Draft SC 705-4 published 5/1979)

02/1983

1.151

Instrument Sensing Lines (Draft IC 126-5 published 3/1982)

07/1983

1.152

Criteria for Digital Computers in Safety Systems of Nuclear Power Plants (Draft IC 127-5 published 3/1983) (Draft DG-1039, Proposed Revision 1, 1 01/1996 published 5/1995)

01/1996

1.153

Criteria for Safety Systems (Draft I C 609-5 published 12/1982) (Draft DG-1042, Proposed Revision 1, published 11/1995)

06/1996

1.154

Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors (Draft SI 502-4 published 1/1986)

01/1987

1.155

Station Blackout (Draft SI 501-4 published 3/1986) (Issued June 1988, reissued August 1988 with corrected tables)

08/1988

1.156

Environmental Qualification of Connection Assemblies for Nuclear Power Plants (Draft EE 404-4 published 5/1987)

11/1987

1.157

Best-Estimate Calculations of Emergency Core Cooling System Performance (Draft RS 701-4 published 3/1987)

05/1989

1.158

Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants (Draft EE 006-5 published 8/1987)

02/1989

1.159

Assuring the Availability of Funds for Decommissioning Nuclear Reactors (Draft DG-1003 published 5/1989)

08/1990

1.160

Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Draft DG-1020 published 11/1992) (Draft DG-1031, Proposed Revision 1, published 6/1994) (Draft DG-1051, Proposed Revision 2, published 8/1996)

03/1997

1.161

Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb (Draft DG-1023 published 9/1993)

06/1995

1.162

Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels (Draft DG-1027 published 10/1994)

02/1996

1.163

Performance-Based Containment Leak-Test Program (Draft DG-1037 published 2/1995) (Errata to NEI 94-01 published 3/1996)

09/1995

1.164

(Not yet issued)

 

1.165

Identification and Characterization of Seismic Sources and Determination Safe Shutdown Earthquake Ground Motion (Draft DG-1015 issued 11/1992, Draft DG-1032, issued 2/1995)

03/1997

1.166

Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions (Draft DG-1017 issued 11/1992, Draft DG-1034 issued 2/1995)

03/1997

1.167

Restart of a Nuclear Power Plant Shut Down by a Seismic Event (Draft DG-1018 issued 11/1992, Draft DG-1035 issued 2/1995)

03/1997

1.168

Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1054 issued 8/1996)

09/1997

1.169

Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1055 issued 8/1996)

09/1997

1.170

Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1056 issued 8/1996)

09/1997

1.171

Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1057 issued 8/1996)

09/1997

1.172

Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1058 issued 8/1996)

09/1997

1.173

Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1059 issued 8/1996)

09/1997

1.174

An Approach for using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis (Draft DG-1061 issued 6/97)

07/1998

1.175

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (Draft DG-1062 issued 6/97)

08/1998

1.176

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance (Draft DG-1064 issued 6/97)

08/1998

1.177

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications (Draft DG-1065 issued 6/97)

08/1998

1.178

An Approach For Plant-Specific Risk-informed Decisionmaking Inservice Inspection of Piping (Draft DG-1063 issued 10/97)

09/1998

1.179

Standard Format and Content of License Termination Plans for Nuclear Power Reactors

01/1999

1.180

Guidelines for Evaluating Electromagnetic and Radiofrequency Interference in Safety-related Instrumentation and Control Systems

05/2000

1.181

Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)

 

1.183

Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors

07/2000

1.184

Decommissioning of Nuclear Power Reactors

 

1.185

Standard Format and Content for Post-Shutdown Decommissioning Activities Report

09/1999

1.186

Guidance and Examples for Identifying 10 CFR 50.2 Design Bases

12/2000

1.187

Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments

11/2000

1.188

Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses

07/2001

1.189

Fire Protection for Nuclear Power Plants

04/2001

1.190

Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence

03/2001

1.191

Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown

05/2001

1.192

Operation and Maintenance Code Case Acceptability, ASME OM Code

06/2003

1.193

ASME Code Cases Not Approved for Use

06/2003

1.194

Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants

06/2003

1.195

Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants

06/2003

1.196

Control Room Habitability at Light-Water Nuclear Power Reactors

01/2007

1.197

Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors

05/2003

1.198

Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites

11/2003

1.199

Anchoring Components and Structural Supports in Concrete

11/2003

1.200

An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,

01/2007

1.201

Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance

05/2006

1.202

Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors

02/2005

1.203

Transient and Accident Analysis Methods

12/2005

1.204

Guidelines for Lightning Protection of Nuclear Power Plants

11/2005

1.205

Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants

 

1.206

Combined License Applications for Nuclear Power Plants (LWR Edition).

 

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

 

1.208

A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion

 

1.209

Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants

 

1.210

Qualification of Safety-Related BatteryChargers and Inverters for Nuclear Power Plants

06/2008