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NRC Regulatory Guides - Fuels and Materials Facilities (Division 3)

This page lists the number, title, publication date, and revisions for each regulatory guide in Division 3, "Fuels and Materials Facilities," with references to draft guides and related documents (where applicable).

See also Draft Regulatory Guides for Division 3.

See NRC Regulatory Guides for more general information.

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Guide
Number
Title Rev. Publish Date Last Evaluation
3.1 (Withdrawn)
  • Revision 2 of Regulatory Guide 3.1, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.2 (Withdrawn -- See 63 FR 2426, 01/15/1998)
  • Revision 0 of Regulatory Guide 3.2, "Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particles," was published 01/1973 and subsequently withdrawn 01/15/1998
W 01/1998 01/1998
-- --
3.3 Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants 1 03/1974 04/2009
-- 01/1973
3.4 (Withdrawn)
  • Revision 2 of Regulatory Guide 3.4, "Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and Materials Facilities," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)


  • Revision 2 of Regulatory Guide 3.4, published 03/1986, superseded Regulatory Guide 3.41 (see details below)
W 08/1998 08/1998
-- --
3.5 Standard Format and Content of License Applications for Uranium Mills (for Comment)
  • Draft WM 039-4, Proposed Revision 2, published 08/1981
1 11/1977 08/2008
-- 02/1973 04/2009
3.6 Content of Technical Specifications for Fuel Reprocessing Plants -- 04/1973 04/2009
3.7 Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants -- 03/1973 04/2009
3.8 Preparation of Environmental Reports for Uranium Mills 2 10/1982 02/2008
1 09/1978
-- 04/1973
3.9 (Withdrawn -- See 63 FR 2426, 01/15/1998)
  • Revision 0 of Regulatory Guide 3.9, "Concrete Radiation Shields," was published 06/1973 and subsequently withdrawn 01/15/1998
W 01/1998 01/1998
-- --
3.10 Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants -- 06/1973 04/2009
3.11 Design, Construction, and Inspection of Embankment Retention Systems at Uranium Recovery Facilities
  • Prior to the issuance of Revision 3, RG 3.11 was entitled "Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills"
3 11/2008 11/2008
2 12/1977
1 03/1977
-- 06/1973
3.11.1 Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings
(Withdrawn -- See 73 FR 66686, 11/10/2008)
W 11/2008 11/2008
1 10/1980
-- --
3.12 General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants -- 08/1973 06/2008
3.13 Guide for Acceptable Waste Storage Methods at UF6 Production Plants -- 10/1973 08/2009
3.14 Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants -- 10/1973 07/2008
3.15 Standard Format and Content of License Applications for Storage Only of Unirradiated Power Reactor Fuel and Associated Radioactive Material
  • Draft CE 219-4, Proposed Revision 1, published 08/1982
1 04/1983
-- 10/1973
3.16 General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants 1 04/2009 04/2009
-- 01/1974
3.17 Earthquake Instrumentation for Fuel Reprocessing Plants -- 02/1974 07/2008
3.18 Confinement Barriers and Systems for Fuel Reprocessing Plants -- 02/1974 04/2009
3.19 Reporting of Operating Information for Fuel Reprocessing Plants -- 02/1974
3.20 Process Offgas Systems for Fuel Reprocessing Plants -- 02/1974 04/2009
3.21 Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing and to Plutonium Processing and Fuel Fabrication Plants -- 03/1974 04/2009
3.22 Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions -- 06/1974 10/1986
3.23 (Withdrawn -- See 45 FR 71876, 10/30/1980) W 10/1980 01/1980
3.24 (Withdrawn -- See 46 FR 14507, 02/27/1981) W 02/1981 02/1981
3.25 Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities 1 12/2008 12/2008
-- 12/1974
3.26 Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants -- 02/1975 04/2009
3.27 Nondestructive Examination of Welds in the Liners of Concrete Barriers in Fuel Reprocessing Plants 1 05/1977 04/2009
-- 05/1975
3.28 Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants -- 05/1975 04/2009
3.29 Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants -- 05/1975 04/2009
3.30 Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants O-R 05/1977 04/2009
-- 06/1975
3.31 Emergency Water Supply Systems for Fuel Reprocessing Plants O-R 05/1977 07/2008
-- 09/1975
3.32 General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (for Comment) -- 09/1975 04/2009
3.33 (Withdrawn -- See 63 FR 2426, 01/15/1998)
  • Revision 0 of Regulatory Guide 3.33, "Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant," was published for comment in 04/1977 and subsequently withdrawn on 01/15/1998
W 01/1998 01/1998
-- --
3.34 (Withdrawn -- See 63 FR 2426, 01/15/1998)
  • "Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant"
W 01/1998 01/1998
-- --
3.35 (Withdrawn -- See 63 FR 2426, 01/15/1998)
  • Revision 1 of Regulatory Guide 3.35, "Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant," was published in 07/1979 and subsequently withdrawn on 01/15/1998
W 01/1998 01/1998
-- --
3.36 (Withdrawn -- See 44 FR 6535, 02/01/1979) W 02/1979 02/1979
3.37 Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (for Comment) -- 09/1975 04/2009
3.38 General Fire Protection Guide for Fuel Reprocessing Plants (for Comment)
(Withdrawn -- See 73 FR 76420, 12/16/2008)
W

12/2008

12/2008
-- 06/1976
3.39 Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants -- 01/1976
3.40 Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants 1 12/1977 04/2009
-- 11/1976
3.41 (Withdrawn -- See 51 FR 11660, 04/04/1986) W 04/1986 04/1986
3.42 Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70
(Withdrawn -- See 73 FR 34964, 06/19/2008)
W 06/2008 06/2008
1 09/1979
-- --
3.43 (Withdrawn)
  • Revision 1 of Regulatory Guide 3.43, "Nuclear Criticality Safety in the Storage of Fissile Materials," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.44 Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)
  • Draft CE 403-4, Proposed Revision 2, published 11/1986
2 01/1989
1 11/1980
-- 12/1978
3.45 (Withdrawn)
  • Revision 1 of Regulatory Guide 3.45, "Nuclear Criticality Safety for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.46 Standard Format and Content of License Applications, Including Environmental Reports, for In Situ Uranium Solution Mining
  • Draft FP 818-4, Proposed Revision 0, published 07/1980
-- 06/1982
3.47 (Withdrawn)
  • Revision 0 of Regulatory Guide 3.47, "Nuclear Criticality Control and Safety of Homogeneous Plutonium-Uranium Fuel Mixtures Outside Reactors," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.48 Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Installation (Dry Storage)
  • Draft CE 406-4, Proposed Revision 1, published 10/1986
  • Draft FP 029-4, Proposed Revision 0, published 12/1980
1 08/1989 01/2009
-- 10/1981
3.49 Design of an Independent Spent Fuel Storage Installation (Water-Basin Type)
  • Draft FP 806-6, Proposed Revision 0, published 01/1981
-- 12/1981
3.50 Standard Format and Content for a License Application To Store Spent Fuel and High-Level Radioactive Waste
  • Draft CE 402-4, Proposed Revision 1, published 09/1986
  • Draft FP 907-4, Proposed Revision 0, published 03/1981
1 09/1989
-- 01/1982
3.51 Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations
  • Errata to Revision 0, published 08/1982
  • Draft RH 802-4, Proposed Revision 0, published 05/1979
-- 03/1982
3.52 Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Processing and Fuel Fabrication 2 05/2009 05/2009
1 11/1986
-- 07/1982
3.53 Applicability of Existing Regulatory Guides to the Design and Operation of an Independent Spent Fuel Storage Installation
  • Draft CE 037-4, Proposed Revision 0, published 11/1981
-- 07/1982
3.54 Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation
  • DG-3010, Proposed Revision 1, published 09/1997
  • Draft CE 034-4, Second Proposed Revision 0, published 01/1983
  • Draft FP 034-4, First Proposed Revision 0, published 12/1980
1 01/1999
-- 09/1984
3.55 Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Hexafluoride Production
  • Draft CE 227-4, Proposed Revision 0, published 01/1984
-- 04/1985
3.56 General Guidance for Designing, Testing, Operating, and Maintaining Emission Control Devices at Uranium Mills
  • Draft CE 309-4, Proposed Revision 0, published 05/1985
-- 05/1986
3.57 (Withdrawn)
  • Revision 0 of Regulatory Guide 3.57, "Administrative Practices for Nuclear Criticality Safety at Fuels and Materials Facilities," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.58 (Withdrawn)
  • Revision 0 of Regulatory Guide 3.58, "Criticality Safety for Handling, Storing, and Transporting LWR Fuel at Fuels and Materials Facilities," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.59 Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations
  • Draft WM 407-4, Proposed Revision 0, published 04/1986
-- 03/1987
3.60 Design of an Independent Spent Fuel Storage Installation (Dry Storage)
  • Draft CE 410-4, Proposed Revision 0, published 11/1985
-- 03/1987
3.61 Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask
  • Draft CE 306-4, Proposed Revision 0, published 04/1986
-- 02/1989
3.62 Standard Format and Content for the Safety Analysis Report for Onsite Storage of Spent Fuel Storage Casks
  • Draft CE 301-4, Proposed Revision 0, published 04/1986
-- 02/1989
3.63 Onsite Meteorological Measurement Program for Uranium Recovery Facilities -- Data Acquisition and Reporting
  • Draft ES 401-4, Proposed Revision 0, published 09/1985
-- 03/1988 11/2009
3.64 Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings Covers
  • Draft WM 503-4, Proposed Revision 0, published 05/1987
-- 06/1989 12/2008
3.65 Standard Format and Content of Decommissioning Plans for Materials Licensees
  • Prior to the issuance of Revision 1, RG 3.65 was entitled "Standard Format and Content of Decommissioning Plans for Licensees Under 10 CFR Parts 30, 40, and 70"
1 05/2008 05/2008
-- 08/1989
3.66 Standard Format and Content of Financial Assurance Mechanisms
  • Prior to the issuance of Revision 1, RG 3.66 was entitled "Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning Under 10 CFR Parts 30, 40, 70, and 72"
1 05/2008 05/2008
-- 06/1990
3.67 Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities
  • DG-3005, Proposed Revision 0, published 09/1990
-- 01/1992
3.68 (Withdrawn)
  • Revision 0 of Regulatory Guide 3.68, "Nuclear Criticality Safety Training," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)
W 08/1998 08/1998
-- --
3.69 Topical Guidelines for the Licensing Support Network
  • DG-3022, Proposed Revision 1, published 06/2002
  • DG-3009, Proposed Revision 0, published 07/1993
1 06/2004 04/2009
-- 09/1996
3.70 (Withdrawn)
  • Revision 0 of Regulatory Guide 3.70, "Use of Fixed Neutron Absorbers at Fuels and Materials Facilities," was superseded by Regulatory Guide 3.71, dated 08/1998 (see details below)

W

08/1998 08/1998
-- --
3.71 Nuclear Criticality Safety Standards for Fuels and Material Facilities
  • DG-3023, Proposed Revision 1, published 05/2005
  • DG-3013, Proposed Revision 0, published 01/1998
1 10/2005
-- 08/1998
3.72 Guidance for Implementation of 10 CFR 72.48, Changes, Tests, and Experiments
  • DG-3020, Proposed Revision 0, published 12/2000
-- 03/2001
3.73 Site Evaluations and Design Earthquake Ground Motion for Dry Cask Independent Spent Fuel Storage and Monitored Retrievable Storage Installations
  • DG-3021, Proposed Revision 0, published 07/2002
-- 10/2003


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