| Date |
Title |
| 12/18/2006 |
Draft Final Regulatory Guide 1.207 (DG-1144), “Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors”
|
| 12/15/2006 |
Proposed Revision to Standard Review Plan Section 13.3, “Emergency Planning” |
| 12/15/2006 |
Proposed Revisions to Standard Review Plan Sections in
Support of New Reactor Licensing |
| 12/12/2006 |
Draft Final Regulatory Guide Dg-1145, Combined License Applications for Nuclear Power Plants (LWR Edition) |
| 11/17/2006 |
Draft Final Revision 3 to Regulatory Guide 1.7, "Control of
Combustible Gas Concentrations in Containment Following a
Loss-of-Coolant Accident," and Standard Review Plan Section
6.2.5, "Combustible Gas Control in Containment"
|
| 11/17/2006 |
Proposed Revision 1 to Regulatory Guide 1.189 (DG-1170), "Fire Protection for Nuclear Power Plants" |
| 11/17/2006 |
Report on the Safety Aspects of the License Renewal Application for the Palisades Nuclear Power Plant |
| 11/16/2006 |
Draft Final Rule to Risk-inform 10 Cfr 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Lightwater Nuclear Power Reactors" |
| 11/07/2006 |
Browns Ferry Nuclear Plant, Unit 1 - Extended Power Uprate Application and Supplemental Application |
| 11/06/2006 |
Proposed Revisions to Standard Review Plan Sections in Support of New Reactor Licensing |
| 11/03/2006 |
Proposed Revisions to Regulatory Guides in Support of New Reactor Licensing |
| 10/25/2006 |
Draft Final NUREG-1824, "Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications"
|
| 10/23/2006 |
Draft Revision 1 to Regulatory Guide 1.200 (DG-1161), "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," and SRP Section 19.1, "Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" |
| 10/17/2006 |
ACRS Assessment of the Quality of Selected NRC Research Projects- FY 2006 |
| 10/16/2006 |
Proposed Revisions to Regulatory Guides in Support of New Reactor Licensing Activities |
| 10/13/2006 |
Supplement 1 to Final Safety Evaluation Report for North Anna Early Site Permit (ESP) Application |
| 10/06/2006 |
Draft Final Revisions to 10 CFR Part 26, "Fitness-for-Duty
Programs" |
| 09/22/2006 |
Lessons Learned from the Review of Early Site Permit
Applications |
| 09/21/2006 |
Proposed Direct Final Rule to Amend 10 CFR 50.68,
"Criticality Accident Requirements" |
| 09/19/2006 |
Report on the Safety Aspects of the License Renewal
Application for the Monticello Nuclear Generating
Plant |
| 09/13/2006 |
Draft Final Revision to Regulatory Guide 1.76, "Design
Basis Tornado for Nuclear Power Plants" |
| 09/13/2006 |
Draft NUREG-1852, "Demonstrating the Feasibility and
Reliability of Operator Manual Actions in Response to
Fire" |
| 09/13/2006 |
Proposed Revision to Regulatory Guide 1.23 (DG-1164),
"Meteorological Monitoring Programs for Nuclear
Power Plants" |
| 09/13/2006 |
Proposed Revision to Standard Review Plan, NUREG-0800,
Section 6.1.1, "Engineered Safety Features Materials" |
| 09/13/2006 |
Questions Raised by Members of the Public During the ACRS
Subcommittee Meeting on Palisades Nuclear Plant License Renewal
Application |
| 08/02/2006 |
Report on the Safety Aspects of the License Renewal Application for the Nine Mile Point Nuclear Station, Units 1 and 2 |
| 08/02/2006 |
Draft NUREG Report, "Integrating Risk and Safety Margins" |
| 08/01/2006 |
Generic Safety Issue 191- Assessment of Debris Accumulation on PWR Sump Performance |
| 07/14/2006 |
Draft Final Rule Package to Amend 10 CFR 50.68, "Criticality Accident Requirement" |
| 07/14/2006 |
Proposed Revision to Standard Review Plan NUREG-0800, Section 3.9.4, "Control Rod Drive Systems" |
| 06/21/2006 |
Results of the Staff's Initial Screening of Generic Issue-197, "Iodine Spiking Phenomena" |
| 06/16/2006 |
Draft Final Generic Letter 2006-XX: Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations |
| 06/15/2006 |
Draft Final Generic Letter 2006-XX, "Inaccessible or Underground Cable Failures that Disable Accident Mitigation Systems" |
| 06/06/2006 |
Draft Final Revision 1 to Regulatory Guide 8.38, "Control of Access to High and Very High Radiation Areas in Nuclear Power Plants" |
| 05/22/2006 |
R.E. Ginna Extended Power Uprate Application |
| 05/22/2006 |
Beaver Valley Extended Power Uprate Application |
| 05/22/2006 |
Proposed Revisions to 10 CFR Part 52: Licenses, Certifications, and Approvals for Nuclear Power Plants, and Conforming Amendments to Applicable NRC Regulations |
| 05/17/2006 |
Modified Draft Final Revision 4 to Regulatory Guide 1.97, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants" |
| 05/17/2006 |
Report on the Safety Aspects of the License Renewal Application for the Brunswick Steam Electric Plant, Units 1 and 2 |
| 05/08/2006 |
ACRS Review of the Clinton Early Site Permit Application - Final Safety Evaluation Report Changed Pages Prior to Publishing as a NUREG |
| 05/05/2006 |
Draft Regulatory Guide DG-1144, "Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors" |
| 04/21/2006 |
Application of the TRACG Computer Code to Evaluate the Stability of the Economic Simplified Boiling Water Reactor |
| 04/21/2006 |
NRC Staff's Proposed Approach to Enhance the Reactor Oversight Process to Address Safety Culture Issues |
| 04/20/2006 |
Draft Final Regulatory Guide 1.205, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants" |
| 04/19/2006 |
Response to Your March 29, 2006 Letter Regarding Standard Review Plan, Section 14.2.1, "Generic Guidelines for Extended Power Uprate Testing Programs" |
| 04/14/2006 |
Grand Gulf Early Site Permit Application: Evaluation of Transportation Accidents on the Mississippi River |
| 04/14/2006 |
Review of the 1994 Addenda to the ASME Code for Class 1, 2, and 3 Piping Systems and the Resolution of the Differences Between the NRC Staff and ASME |
| 04/10/2006 |
Generic Safetiy Issue 191 - Assessment of Debris Accumulation on PWR Sump Peformance |
| 03/28/2006 |
Draft Final Revision 4 to Regulatory Guide 1.97, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants" |
| 03/24/2006 |
Final Review of the Exelon Generation Company, LLC, Application for Early Site Permit and the Associated NRC Staff's Final Safety Evaluation Report |
| 03/23/2006 |
Report on the Safety Aspects of the License Renewal Application for the Browns Ferry Nuclear Plant Units 1, 2, and 3 |
| 03/17/2006 |
Resolution of Generic Safety Issue 188, "Steam Generator Tube Leaks or Ruptures Concurrent with Containment Bypass from Main Steam or Feedwater Line Breaches" |
| 03/15/2006 |
Review and Evaluation of the NRC Safety Research Program |
| 02/22/2006 |
Standard Review Plan, Section 14.2.1, "Generic Guidelines for Extended Power Uprate Testing Programs" |
| 02/22/2006 |
Draft NUREG Report, "Evaluation of Human Reliability Analysis Methods Against Good Practices" |
| 02/14/2006 |
Proposed Revisions to Regulatory Guides Regarding ASME Code Cases |
| 02/14/2006 |
Draft Final Revision 2 to Regulatory Guide 1.92, "Combining Modal Responses and Spatial Components in Seismic Response Analysis" |
| 01/04/2006 |
Vermont Yankee Extended Power Uprate |
