Division 3 --Fuels and Materials Facilities

Guide
Number

Title

Publish
Date

 

3.1

(Withdrawn - See RG 3.71)

--

 

3.2

(Withdrawn--See 63 FR 2426) (Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particles

--

 

3.3

Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants

03/1974

3.4

(Withdrawn - See RG 3.71)

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3.5

Standard Format and Content of License Applications for Uranium Mills (for Comment) (Draft WM 039-4, Proposed Revision 2, published 8/1981)

11/1977

3.6

Content of Technical Specifications for Fuel Reprocessing Plants

04/1973

 

3.7

Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants

03/1973

 

3.8

Preparation of Environmental Reports for Uranium Mills

10/1982

3.9

(Withdrawn--See 63 FR 2426) (Concrete Radiation Shields)

--

 

3.10

Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants

06/1973

 

3.11

Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills

12/1977

3.11.1

Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings

10/1980

3.12

General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants

08/1973

 

3.13

Guide for Acceptable Waste Storage Methods at UF6 Production Plants

10/1973

 

3.14

Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants

10/1973

 

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 8/1982)

04/1983

3.16

General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants

01/1974

 

3.17

Earthquake Instrumentation for Fuel Reprocessing Plants

02/1974

 

3.18

Confinement Barriers and Systems for Fuel Reprocessing Plants

02/1974

 

3.19

Reporting of Operating Information for Fuel Reprocessing Plants

02/1974

 

3.20

Process Offgas Systems for Fuel Reprocessing Plants

02/1974

 

3.21

Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing and to Plutonium Processing and Fuel Fabrication Plants

03/1974

 

3.22

Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions

06/1974

 

3.23

(Withdrawn--See 45 FR 71876, 10/30/1980)

--

 

3.24

(Withdrawn--See 46 FR 14507, 2/27/1981)

--

 

3.25

Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities

12/1974

 

3.26

Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants

02/1975

 

3.27

Nondestructive Examination of Welds in the Liners of Concrete Barriers in Fuel Reprocessing Plants

05/1977

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

 

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

 

3.30

Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants

05/1977

3.31

Emergency Water Supply Systems for Fuel Reprocessing Plants

05/1977

3.32

General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (for Comment)

09/1975

 

3.33

(Withdrawn--See 63 FR 2426) (Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant)

--

 

3.34

(Withdrawn--See 63 FR 2426) (Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant)

--

 

3.35

(Withdrawn--See 63 FR 2426) (Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant

--

 

3.36

(Withdrawn--See 44 FR 6535, 2/1/1979)

--

 

3.37

Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (for Comment)

09/1975

 

3.38

General Fire Protection Guide for Fuel Reprocessing Plants (for Comment)

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

12/1977

3.41

(Withdrawn--See 51 FR 11660, 4/4/1986)

--

 

3.42

Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70 1 09/1979

08/1977

 

3.43

(Withdrawn - See RG 3.71)

--

 

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)

01/1989

3.45

Nuclear Criticality Safety for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials (Draft FP 925-5 published 1/1980) (Draft CE 802-5, Proposed Revision 1, published 5/1988)

04/1989

3.46

Standard Format and Content of License Applications, Including Environmental Reports, for In Situ Uranium Solution Mining (Draft FP 818-4 published 7/1980)

06/1982

 

3.47

(Withdrawn - See RG 3.71)

--

 

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 FP 029-4 published 12/1980) (Draft CE 406-4, Proposed Revision 1, published 10/1986)

08/1989

3.49

Design of an Independent Spent Fuel Storage Installation (Water-Basin Type) (Draft FP 806-6 published 1/1981)

12/1981

 

3.50

Standard Format and Content for a License Application To Store Spent Fuel and High-Level Radioactive Waste (Draft FP 907-4 published 3/1981) (Draft CE 402-4, Proposed Revision 1, published 9/1986)

09/1989

3.51

Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations (Draft RH 802-4 published 5/1979) (Errata published August 1982)

03/1982

 

3.52

Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Processing and Fuel Fabrication (Draft FP 716-4 published 10/1980) (Draft CE 308-4, Proposed Revision 1, published 7/1985)

11/1986

3.53

Applicability of Existing Regulatory Guides to the Design and Operation of an Independent Spent Fuel Storage Installation (Draft CE 037-4 published 11/1981)

07/1982

 

3.54

Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation (Draft FP 034-4 published 12/1980) (Second Draft CE 034-4 published 1/1983) (DG-3010, Proposed Revision 1, published 9/1997)

09/1999

3.55

Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Hexafluoride Production (Draft CE 227-4 published 1/1984)

04/1985

 

3.56

General Guidance for Designing, Testing, Operating, and Maintaining Emission Control Devices at Uranium Mills (Draft CE 309-4 published 5/1985)

05/1986

 

3.57

(Withdrawn - See RG 3.71)

--

 

3.58

(Withdrawn - See RG 3.71)

--

 

3.59

Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations (Draft WM 407-4 published 4/1986)

03/1987

 

3.60

Design of an Independent Spent Fuel Storage Installation (Dry Storage) (Draft CE 410-4 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 published 4/1986)

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 published 4/1986)

02/1989

 

3.63

Onsite Meteorological Measurement Program for Uranium Recovery Facilities -- Data Acquisition and Reporting (Draft ES 401-4 published 9/1985)

03/1988

 

3.64

Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings Covers (Draft WM 503-4 published 5/1987)

06/1989

 

3.65

Standard Format and Content of Decommissioning Plans for Licensees Under 10 CFR Parts 30, 40, and 70 (Draft CE 304-4 published 12/1985)

05/2008

 

3.66

Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning Under 10 CFR Parts 30, 40, 70, and 72 (Draft DG-3002 published 1/1990)

05/2008

 

3.67

Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities (Draft DG-3005 published 9/1990)

01/1992

 

3.68

(Withdrawn - See RG 3.71)

--

 

3.69

Topical Guidelines for the Licensing Support System (Draft DG-3009 published 7/1993)

06/2004

 

3.70

(Withdrawn - See RG 3.71) Use of Fixed Neutron Absorbers at Fuels and Materials Facilities,

--

 

3.71

Nuclear Criticality Safety Standards for Fuels and Material Facilities (Draft DG-3013 published 1/98) (Guide Withdraws Regulatory Guides 3.1, 3.4, 3.43, 3.45, 3.47, 3.57, 3.58, 3.68, 3.70 and 8.12)

10/2005

 

3.72

Guidance for Implementation of 10 CFR 72.48, Changes, Tests, and Experiments

03/2001

 

3.73

Site Evaluations and Design Earthquake Ground Motion for Dry Cask Independent Spent Fuel Storage and Monitored Retrievable Storage Installations

10/2003