United States Nuclear Regulatory Commission - Protecting People and the Environment

Advisory Committee on Reactor Safeguards (ACRS) 2002 Letter Reports


DateTitle
12/20/2002Draft Final American Nuclear Society External Events Probabilistic Risk Assessment Methodology Standard
12/20/2002Framatome ANP S-RELAP5 Realistic Large-Break Loss-of-Coolant Accident Code
12/18/2002 Report on the Safety Aspects of the License Renewal Applications for the North Anna Power Station Units 1 And 2 and the Surry Power Station Units 1 And 2
12/13/2002Draft Commission Paper on Policy Issues Related to Non-Light-Water Reactor Designs
11/19/2002Draft Regulatory Guide DG-1123, "Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"
11/13/2002 Recommendations Proposed by the Office of Nuclear Regulatory Research for Resolving Generic Safety Issue-189, "Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident"
10/17/2002Draft Report "Guidance for Performance-Based Regulation"
10/17/2002Confirmatory Research Program on High-Burnup Fuel
10/01/2002Draft Regulatory Guide DG-1120 and Standard Review Plan Section 15.0.2 Concerning NRC Reviews of Transient and Accident Analysis Methods
09/24/2002Human Factors and Human Reliability Analysis Research Plans
09/18/2002Proposed Rulemaking on 10 CFR 50.69, Draft Regulatory Guide DG-1121, and NEI 00-04
09/17/2002 Draft Regulatory Guide DG-1122, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities"
07/23/2002Draft Final Revision 1 to Regulatory Guide 1.174 and to Chapter 19 of the Standard Review Plan
07/18/2002Risk Metrics and Criteria for Reevaluating the Technical Basis of the Pressurized Thermal Shock Rule
07/18/2002Draft Advanced Reactor Research Plan
07/16/2002Draft Regulatory Guide DG-1119 (Proposed Revision 1 to Regulatory Guide 1.180), Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems
06/20/2002Vessel Head Penetrations and Vessel Head Degradation
06/17/2002Recommendations Proposed by the Office of Nuclear Regulatory Research for Resolving Generic Safety Issue-189, "Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident"
06/17/2002Proposed Technical Assessment of Generic Safety Issue-168, "Environmental Qualification of Low-Voltage Instrumentation and Control Cables"
06/17/2002Proposed Revision to 10 CFR 50.48 Endorsing NFPA-805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants"
06/17/2002Policy Issues Related to Advanced Reactor Licensing
05/10/2002Core Power Uprate for the Brunswick Steam Electric Plant Units 1 and 2
05/8/2002Phebus-FP Program
05/7/2002Proposed NRC Generic Letter 2002-XX: Control Room Envelope Habitability
04/19/2002Draft Final Amendment to 10 CFR 50.55a, "Codes and Standards"
04/19/2002Report on the Safety Aspects of the License Renewal Application for the Turkey Point Nuclear Plant, Units 3 and 4
04/17/2002Criteria for the Treatment of Individual Requirements in a Regulatory Analysis
04/17/2002 GE Nuclear Energy Licensing Topical Report, NEDC-33004P, "Constant Pressure Power Uprate" (Revision 1)
04/16/2002Draft Regulatory Guide DG-1118 (Proposed Revision 1 to Regulatory Guide 1.53), "Application of the Single-Failure Criterion to Safety Systems"
03/19/2002Proposed Rulemaking and Associated Guidance for Risk-informing the Special Treatment Requirements of 10 CFR Part 50 (Option 2)
03/14/2002Phase 2 Pre-application Review for AP1000 Passive Plant Design
03/14/2002Confirmatory Research Program on High-Burnup Fuel
03/14/2002Core Power Uprate for Clinton Power Station, Unit 1
03/14/2002Core Power Uprate for Arkansas Nuclear One, Unit 2
03/13/2002Final Rule on Decommissioning Trust Provisions
02/14/2002Reevaluation of the Technical Basis for the Pressurized Thermal Shock Rule
02/14/2002Review and Evaluation of the Nuclear Regulatory Commission's Safety Research Program
02/13/2002The Revised Reactor Oversight Process
02/12/2002 Proposed Amendment to 10 CFR 50.55a to Incorporate by Reference ASME Boiler and Pressure Vessel and OM Code Cases
Page Last Reviewed/Updated Thursday, July 25, 2013