United States Nuclear Regulatory Commission - Protecting People and the Environment

Advisory Committee on Reactor Safeguards (ACRS) 2007 Letter Reports

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Date Title
12/27/2007 AREVA Detect and Suppress Stability Solution and Methodology
12/20/2007 Draft Final NUREG-1829, "Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process," and Draft NUREG-XXXX, "Seismic Considerations for the Transition Break Size
12/20/2007 Susquehanna Steam Electric Station Units 1 and 2 Extended Power Uprate Application
11/20/2007 Interim Letter: Southern Nuclear Operating Company Application for the Vogtle Early Site Permit and the Associated NRC Safety Evaluation Report with Open Items
11/20/2007 Interim Letter: Chapters 2, 5, 8, 11, 12, and 17 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Certification of the ESBWR Design
11/19/2007 Staff's Implementation of Lessons Learned from Reviews of Early Site Permit Applications
10/19/2007 NRC Staff's Safety Assessment of the Industry Study Related to Dissimilar Metal Weld Issues in Pressurizer Nozzles
10/19/2007 Draft Final Generic Letter 2007-XX, "Managing Gas Intrusion in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems"
10/19/2007 ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2007
10/16/2007 Digital Instrumentation and Control Systems Project Plan and Interim Staff Guidance
10/10/2007 Proposed Revision to Regulatory Guide 1.100, "Seismic Qualification of Electric and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants"
09/26/2007 Development of a Technology-Neutral Regulatory Framework
09/26/2007 Proposed Recommendation for Resolving Generic Issue 156.6.1, 'Pipe Break Effects on Systems and Components Inside Containment'
09/26/2007 Report on the Safety Aspects of the License Renewal Application for the Pilgrim Nuclear Power Station
09/13/2007 Draft Final Amendment to 10 CFR 50.55a, 'Codes and Standards,' and Revisions to Regulatory Guides Regarding ASME Code Cases
07/27/2007 Draft NUREG/CR, Review of NUREG-0654, Supplement 3, "Criteria for Protective Action Recommendations for Severe Accidents"
07/24/2007 Staff Approach to Verifying the Closure of Inspections, Tests, Analyses, and Appectance Criteria Through a Sample-based Inspection Program
07/13/2007 Revisions to Draft Final NUREG-1852, “Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire”
06/22/2007 General Electric (GE) Licensing Topical Reports on Maximum Extended Load Line Limit Analysis plus (Mellla+) and Applicability of GE Methods to Expanded Operating Domains
06/18/2007 Draft Final NUREG-1852, "Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire"
06/12/2007 Draft Regulatory Guide DG-4012, "Minimization of Contamination and Radioactive Waste Generation in Support of Decommissioning"
06/12/2007 Draft Regulatory Guide DG-5019, "Reporting of Safeguards Events"
06/12/2007 Review of the Final Rule to Amend 10 CFR Parts 19, 20 and 50: Occupational Dose Records, Labeling Containers, and the Total Effective Dose Equivalent (TEDE)
06/12/2007 Draft Regulatory Guide DG-5021, "Managing the Safety/security Interface"
06/12/2007 Draft Regulatory Guide DG-1148, "Qualification of Safety-related Battery Chargers and Inverters for Nuclear Power Plants"
05/23/2007 Proposed Technical Basis for the Revision to 10 CFR 50.46 LOCA Embrittlement Criteria for Fuel Cladding Materials
05/18/2007 Activities Related to Digital Instrumentation and Control Systems
05/16/2007 Draft Commission Paper on Staff Plan Regarding a Risk-Informed And Performance-Based Revision to 10 CFR Part 50
05/16/2007 Development of an Integrated Long-Term Regulatory Research Plan
05/08/2007 Draft Regulatory Guide DG-1132, “Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants”
05/08/2007 Draft Regulatory Guide DG-1173, “Guidance on Monitoring and Responding to Reactor Coolant System Leakage”
04/23/2007 Risk-Informed Technical Specifications Initiative 4B, Riskmanaged Technical Specifications (RMTS) Guidelines
04/23/2007 Revision 3 to Standard Review Plan Section 4.2, "Fuel System Design"
04/23/2007 Human Reliability Analysis Models
04/20/2007 Technology-Neutral Framework for Future Plant Licensing
04/10/2007 Proposed Rule to Amend 10 CFR 50.61, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events"
03/22/2007 Development of the Trace Thermal-Hydraulic System Analysis Code
03/22/2007 Proposed NRC Staff and Industry Activities for Addressing Dissimilar Metal Weld Issues Resulting from the Wolf Creek Pressurizer Weld Inspection Results
03/22/2007 Proposed Revision 3 to Standard Review Plan Section 15.0, "Introduction - Transient and Accident Analyses"
03/22/2007 Proposed Revision to Standard Review Plan Section 15.9, "BWR Stability"
03/14/2007 Comments Regarding Staff Review of Thermal-Hydraulic Methodologies
03/14/2007 Proposed Revisions to Standard Review Plan Sections in Support of New Reactor Licensing
03/09/2007 Proposed Revision to 10 CFR 50.55A "Codes and Standards"
02/16/2007 Browns Ferry Nuclear Power Plant, Unit 1, 5-Percent Power Uprate
02/14/2007 Draft Final Revision 1 to Regulatory Guide 1.189 (DG-1170), "Fire Protection for Nuclear Power Plants"
02/08/2007 Report on the Safety Aspects of the License Renewal Application for the Oyster Creek Generating Station
02/06/2007 Proposed Revisions to Standard Review Plan Sections in Support of New Reactor Licensing
01/19/2007 Proposed Generic Letter 2007-xx, “Managing Gas Intrusion in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems"
Page Last Reviewed/Updated Monday, May 05, 2014