| Date |
Title |
EDO
Response |
| 12/13/2011 |
Revised Branch Technical Position on Concentration Averaging and Encapsulation of Low-Level Radioactive Waste |
02/03/2012 |
| 12/12/2011 |
Response to the October 28, 2011, EDO Letter Regarding the ACRS Recommendations on Topical Report NEDC-33173P, Supplement 2, Parts 1, 2, and 3, "Analysis of Gamma Scan Data and Removal of Safety Limit Critical Power Ratio (SLMCPR) Margin" |
01/16/2012 |
| 12/08/2011 |
Proposed Requirements for ITAAC Maintenance and Draft Final Regulatory Guide 1.215, "Guidance for ITAAC Closure Under 10 CFR Part 62" |
01/16/2012 |
| 12/07/2011 |
Report on the Safety Aspects of the Progress Energy Florida, Inc. Combined License Application for Levy Nuclear Plant, Units 1 and 2 |
01/24/2012 |
| 12/06/2011 |
ESBWR Design Certification Rulemaking and Supplemental Final Safety Evaluation Report |
No Response Required |
| 12/06/2011 |
Proposed Revisions to Regulatory Guides 1.140 and 1.185 |
No Response Required |
| 11/14/2011 |
Draft Final Revision 6 of Standard Review Plan Branch Technical Position 7-19, "Guidance for Evaluation of Diversity and Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems" |
01/27/2012 |
| 11/14/2011 |
Topical Report NEDC-33173P-A, Supplement 2, Parts 1, 2, and 3, "Analysis of Gamma Scan Data and Removal of Safety Limit Minimum Critical Power Ratio (SLMCPR) Margin" |
Non-publically Available |
| 11/14/2011 |
Draft Final Regulatory Guide 1.106 |
No Response Required |
| 11/14/2011 |
Proposed Revision 4 to Regulatory Guide 1.52 (DG-1274) |
No Response Required |
| 11/10/2011 |
Nine Mile Point Nuclear Station, Unit 2, Extended Power Uprate Application |
12/12/2011 |
| 11/08/2011 |
ACRS Review of Staff's Prioritization of Recommended Actions to be Taken in Response to Fukushima Lessons Learned (SECY-11-0137) |
12/08/2011 |
| 10/17/2011 |
Enhancing the Fuel Cycle Oversight Process |
11/08/2011 |
| 10/17/2011 |
Draft Final Regulatory Guide (RG) 1.82, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident," Revision 4 |
11/21/2011 |
| 10/13/2011 |
Initial ACRS Review of: (1) the NRC Near-Term Task Force Report on Fukushima and (2) Staff's Recommended Actions to be Taken Without Delay |
12/08/2011 |
| 10/12/2011 |
Proposed Closeout – Generic Issue 186, "Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants" |
No Response Required |
| 09/22/2011 |
Final Rule – AP1000 Design Certification Amendment |
No Response Required |
| 09/22/2011 |
Chapters 2, 5, 8, 10,11,12, 13, and 16 of the Safety Evaluation Report with Open Items for Certification of the US-APWR Design |
10/25/2011 |
| 09/22/2011 |
Proposed Rulemaking to Introduce a Site-Specific Performance Assessment and Human Intrusion Analysis Requirement to 10 CFR Part 61 |
11/03/2011 |
| 09/21/2011 |
Proposed Regulatory Guide DG-1278 |
No Response Required |
| 09/20/2011 |
Draft Final Regulatory Guides 1.159, 1.221, and 1.218 |
No Response Required |
| 09/20/2011 |
Supplement 1 to NUREG-1930, "Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Units 2 and 3" |
No Response Required |
| 09/19/2011 |
Draft Final Regulatory Guide 1.115, Revision 2, "Protection Against Turbine Missiles" |
10/25/2011 |
| 09/19/2011 |
ACRS Assessment of the Quality of Selected NRC Research Projects-FY2011 |
|
| 09/19/2011 |
Revision 19 to the AP1000 Design Control Document and the AP1000 Final Safety Evaluation Report |
10/12/2011 |
| 08/11/2011 |
Response to the June 8, 2011, EDO Letter Regarding Draft Final Revision 3 of Regulatory Guide (RG) 1.152, "Criteria for Use of Computers in Safety Systems of Nuclear Power Plants" |
01/30/2012 |
| 08/11/2011 |
Topical Report NEDC-33173P, Supplement 2, Part 1, 2 and 3, "Analysis of Gamma Scan Data and Removal of Safety Limit Minimum Critical Power Ratio (SLMCPR) Margin |
|
| 07/20/2011 |
Information Requested During the April 7, 2011, ACRS Meeting |
|
| 07/20/2011 |
Draft Final Regulatory Guide 1.156 |
No Response Required |
| 07/20/2011 |
Request for Waiver of ACRS Review of Final Rule: U.S. Advanced Boiling Water Reactor Aircraft Impact Design Certification Amendment (RIN 3150-A184) |
08/04/2011 |
| 07/19/2011 |
Supplement 2 to NUREG-1891 |
No Response Required |
| 07/19/2011 |
Proposed Regulatory Guide DG-1270 |
No Response Required |
| 06/22/2011 |
Draft Regulatory Guides DG-1261, DG-1262, and DG-1263 |
|
| 06/22/2011 |
Draft SECY Paper, "Options for Proceeding with Future Level 3 Probabilistic Risk Assessment Activities" |
09/21/2011 |
| 06/16/2011 |
Report on the Safety Aspects of the License Renewal Application for the Hope Creek Generating Station |
07/14/2011 |
| 06/13/2011 |
NRC Bulletin 2011-01, "Mitigating Strategies" |
|
| 06/09/2011 |
Draft Final Regulatory Guides 1.107 and 1.179 |
No Response Required |
| 05/25/2011 |
Report on the Safety Aspects of the License Renewal Application for the Salem Nuclear Generating Station Units 1 and 2 |
06/16/2011 |
| 05/24/2011 |
Human Factors Considerations Associated with Emerging Technologies in Nuclear Power Plants |
06/16/2011 |
| 05/20/2011 |
High Temperature Gas-Cooled Reactor (HTGR) NRC Research Plan |
06/10/2011 |
| 05/19/2011 |
Response to the April 5, 2011, EDO Letter Regarding Draft Final Regulatory Guides 1.34, 1.43, 1.44, and 1.50 |
06/24/2011 |
| 05/19/2011 |
Response to the February 5, 2011, EDO Letter Regarding the Final Safety Evaluation Associated with the Amendment to the AP1000 Design Control Document |
06/30/2011 |
| 05/18/2011 |
Response to the March 1, 2011, EDO Letter Regarding Draft Final Rule, “Enhancements to Emergency Preparedness,” and Related Regulatory Guidance Documents |
06/22/2011 |
| 05/17/2011 |
Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plant, Units 1 and 2, Docket Numbers 50-282 and 50-306 |
|
| 04/20/2011 |
Final Draft Revision 3 of RG 1.152 Criteria for use of Computers in Safety Systems of Nuclear Power Plants |
06/08/2011 |
| 04/19/2011 |
Response to the March 22, 2011, EDO Letter Regarding Comparison of Integrated Safety Analysis and Probabilistic Risk Assessment for Fuel Cycle Facilities |
06/01/2011 |
| 04/19/2011 |
Chapters 2, 4, 5, 8, 10, 11, 12, 16, 17, and 19 of the Safety Evaluation Report with Open Items Associated with the Calvert Cliffs Nuclear Power Plant Unit 3 Combined License Application |
05/19/2011 |
| 04/12/2011 |
Proposed Regulatory Guides DG-1264, DG1206, DG-1207, DG-1208, DG-1209, DG-1210, and DG-1267 |
No Response Required |
| 04/12/2011 |
Draft Final Regulatory Guides 8.2, 8.24, and 3.67 |
No Response Required |
| 04/12/2011 |
Additional Information Regarding The Safety Evaluation Report For The License Renewal Of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 |
|
| 04/12/2011 |
Draft Revision 3 to NUREG-1022, “Event Reporting Guidelines 10 CFR 50.72 and 50.73” |
No Response Required |
| 03/23/2011 |
Status of Groundwater Protection Task Force Efforts |
04/22/2011 |
| 03/23/2011 |
Point Beach Nuclear Plant Units 1 and 2 Extended Power Uprate Application |
04/08/2011 |
| 03/16/2011 |
SECY-11-0024, "Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews" |
03/22/2011 |
| 03/10/2011 |
Draft Final Regulatory Guide 1.149 |
No Response Required |
| 03/10/2011 |
Draft Final Revision to 10 CFR 50.55a, "Codes and Standards" |
|
| 03/10/2011 |
Supplement 2 to NUREG-1907, "Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station, Docket NO. 50-271" |
|
| 03/10/2011 |
Withdrawal of Regulatory Guide 8.5 |
No Response Required |
| 03/01/2011 |
Report on the Safety Aspects of the License Renewal Application for the Palo Verde Nuclear Generating Station |
03/24/2011 |
| 02/28/2011 |
Response to the January 21, 2011, EDO Letter Regarding the Safety Culture Policy Statement |
03/31/2011 |
| 02/24/2011 |
Draft Final Regulatory Guides 1.34, 1.43, 1.44, and 1.50 |
04/05/2011 |
| 02/17/2011 |
Comparison of Integrated Safety Analysis (ISA) to Probabilistic Risk Assessment (PRA) |
03/22/2011 |
| 02/17/2011 |
Report on the Safety Aspects of the South Carolina Electric and Gas Company Combined License Application for V.C. Summer Nuclear Station, Units 2 and 3 |
03/26/2011 |
| 02/17/2011 |
SECY-11-0014, “Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents” |
03/27/2011 |
| 02/17/2011 |
Current State of Licensee Efforts to Transition to National Fire Protection Association (NFPA) Standard 805 |
05/03/2011 |
| 02/17/2011 |
Proposed Regulatory Guide DG-1254 |
No Response Required |
| 01/31/2011 |
Review of RAMONA5-FA For Use in BWR Stability Calculations |
|
| 01/24/2011 |
Draft Final Revision 2 to Regulatory Guide 1.174 and Revision 1 to Regulatory Guide 1.177 |
02/04/2011 |
| 01/24/2011 |
Draft Final Rule, "Enhancements to Emergency Preparedness," and Related Regulatory Guidance Documents |
02/15/2011 |
| 01/24/2011 |
Report on the Safety Aspects of the Southern Nuclear Operating Company Combined License Application for Vogtle Electric Generating Plant, Units 3 and 4 |
03/03/2011 |
| 01/19/2011 |
Report on the Safety Aspects of the Aircraft Impact Assessment for the Westinghouse Electric Company AP1000 Design Certification Amendment Application |
02/09/2011 |
| 01/07/2011 |
Report of the Safety Aspects of the License Renewal Application for the Kewaunee Power Station |
02/09/2011 |