Guide
Number |
Title |
Revision
Number |
Issue
Date |
Additional Information |
1.181 |
Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)
|
0 |
09/1999 |
Reviewed in 2019 – Revise |
1.182 |
Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants
(Withdrawn – See 77 FR 70846, 11/27/2012)
- HISTORY
- 05/2012 – Guidance from RG 1.182 has been incorporated in RG 1.160
- 12/1999 – DG-1082, Proposed Revision 0
|
W |
11/2012 |
|
0 |
05/2000 |
|
1.183 |
Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
|
1 |
10/2023 |
|
0 |
07/2000 |
Reviewed in 2018 – Revise |
1.184 |
Decommissioning of Nuclear Power Reactors
- HISTORY
- 02/2022 – DG-1347 Revision 1, Proposed Revision 2
- 06/2018 – DG-1347, Proposed Revision 2
- 02/2012 – DG-1271, Proposed Revision 1
- 04/2004 – Errata to update Reference 1
- 06/1997 – DG-1067, Proposed Revision 0
|
1 |
10/2013 |
|
0 |
07/2000 |
|
1.185 |
Standard Format and Content for Post-Shutdown Decommissioning Activities Report
- HISTORY
- 02/2022 – DG-1349 Revision 1, Proposed Revision 2
- 06/2018 – DG-1349, Proposed Revision 2
- 12/2012 – DG-1272, Proposed Revision 1
- 04/2004 – Errata to update Reference 1
- 12/1997 – DG-1071, Proposed Revision 0
|
1 |
06/2013 |
|
0 |
07/2000 |
|
1.186 |
Guidance and Examples for Identifying 10 CFR 50.2 Design Bases
|
0 |
12/2000 |
Reviewed in 2017 – No issues identified |
1.187 |
Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments
|
3 |
06/2021 |
|
2 |
06/2020 |
|
1 |
05/2019 |
|
0 |
11/2000 |
Periodic Review
April 2011
No Action |
1.188 |
Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses
- HISTORY
- 09/2019 – DG-1341, Proposed Revision 2
- 04/2015 – Periodic Review of Revision 1 – Issues identified for future consideration
- 04/2010 – Periodic Review of Revision 1 – No issues identified
- 01/2005 – DG-1140, Proposed Revision 1
- 08/2000 – DG-1104, Third Proposed Revision 0
- 08/1996 – DG-1047, Second Proposed Revision 0
- 12/1990 – DG-1009, First Proposed Revision 0
|
2 |
04/2020 |
|
1 |
09/2005 |
|
0 |
07/2001 |
|
1.189 |
Fire Protection for Nuclear Power Plants
- HISTORY
- 11/2020 – DG-1359 Proposed Revision 4
- 04/2009 – DG-1214, Proposed Revision 2
- 11/2006 – DG-1170, Proposed Revision 1
- Prior to the issuance of DG-1170, RG 1.189 was entitled "Fire Protection for Operating Nuclear Power Plants"
- 06/2000 – DG-1097, Second Proposed Revision 0
- 10/1999 – DG-1094, First Proposed Revision 0
|
5 |
10/2023 |
Administrative Change |
4 |
05/2021 |
|
3 |
02/2018 |
Periodic Review – November 2017
- Revise |
2 |
10/2009 |
Periodic Review – December 2014
-Considerations |
1 |
03/2007 |
|
0 |
04/2001 |
|
1.190 |
Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
|
0 |
03/2001 |
Periodic Review 06/2023 –
Considerations
Periodic Review 05/2013 – Considerations
Periodic Review 04/2006 – No Action |
1.191 |
Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown
|
1 |
01/2021 |
|
0 |
05/2001 |
|
1.192 |
Operation and Maintenance Code Case Acceptability, ASME OM Code
|
5 |
03/2024 |
|
4 |
12/2021 |
03/2022: Final Rule Federal Register Notice |
3 |
10/2019 |
03/2020: Final Rule Federal Register Notice |
2 |
03/2017 |
01/2018: Final Rule Federal Register Notice |
1 |
10/2014 |
|
0 |
06/2003 |
|
1.193 |
ASME Code Cases Not Approved for Use
- HISTORY
- 01/2023 – DG-1408, Proposed Revision 8
- 01/2021 – DG-1369, Proposed Revision 7
- 08/2018 – DG-1344, Proposed Revision 6
- 03/2016 – DG-1298, Proposed Revision 5
- 06/2013 – DG-1233, Proposed Revision 4
- 06/2009 – DG-1193, Proposed Revision 3
- 05/2006 – DG-1135, Proposed Revision 2
- 08/2004 – DG-1126, Proposed Revision 1
- 12/2001 – DG-1112, Proposed Revision 0
|
8 |
03/2024 |
|
7 |
12/2021 |
03/2022: Final Rule Federal Register Notice |
6 |
10/2019 |
03/2020: Final Rule Federal Register Notice |
5 |
08/2017 |
01/2018: Final Rule Federal Register Notice |
4 |
10/2014 |
|
3 |
10/2010 |
|
2 |
10/2007 |
|
1 |
08/2005 |
|
0 |
06/2003 |
|
1.194 |
Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants
|
0 |
06/2003 |
Reviewed in 2015 – Issues identified with future consideration |
1.195 |
Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors
|
0 |
05/2003 |
Reviewed in 2016 – No issues identified |
1.196 |
Control Room Habitability at Light-Water Nuclear Power Reactors
|
1 |
01/2007 |
Periodic Review – August 2023 - Considerations |
0 |
05/2003 |
Periodic Review - August 2013 – Considerations |
1.197 |
Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors
|
0 |
05/2003 |
Reviewed in 2015 – No issues identified |
1.198 |
Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites
|
0 |
11/2003 |
Reviewed in 2014 – Issues identified for future consideration |
1.199 |
Anchoring Components and Structural Supports in Concrete
|
1 |
04/2020 |
|
0 |
11/2003 |
|
1.200 |
Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
|
3 |
12/2020 |
|
2 |
03/2009 |
Public Meeting Slides
July 2008 |
1 |
01/2007 |
|
0 |
02/2004 |
|