Click on the folder links to open and access more files.
9 files
|
6.37 MB
| Name Sort descending | Size | Description | |
|---|---|---|---|
| Go up |
Default description
|
||
| Regulatory-Guide-1.183-Rev1 | 1.2 MB |
Revision to "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" with updated source terms to reflect the current understanding of severe accidents and fission product behavior since the publication of RG 1.183 (Oct 2023)
|
|
| Regulatory-Guide-1.183 | 261.09 KB |
Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (July 2000)
|
|
| Regulatory-Guide-1.194 | 219.76 KB |
Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants" (June 2003)
|
|
| Regulatory-Guide-1.195 | 162.93 KB |
Regulatory Guide 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors" (May 2003)
|
|
| Regulatory-Guide-1.196 | 282.69 KB |
Regulatory Guide 1.196, "Control Room Habitability at Light-Water Nuclear Power Reactors" (Jan. 2007)
|
|
| Regulatory-Guide-1.197 | 49.75 KB |
Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors" (May 2003)
|
|
| Regulatory-Guide-1.25 | 2.02 MB |
Regulatory Guide 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)" (Mar. 1972)
|
|
| Regulatory-Guide-1.3 | 1.54 MB |
Regulatory Guide 1.3, Revision 2, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors" (June 1974)
|
|
| Regulatory-Guide-1.4 | 673.08 KB |
Regulatory Guide 1.4, Revision 2, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors" (June 1974)
|