Search by property

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML052520217  + (Rev. 1 to Calculation DRE04-0030, Atmospheric Dispersion Factors (X/Qs) for Accident Release)
• ML052140075  + (Rev. 1 to Calculation E900-03-016, Shonka Discharge & Intake Tunnels FSS Survey Design, Appendix C to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces -Discharge Tunnel SSI,)
• ML052140259  + (Rev. 1 to Calculation E900-05-015, OL1 Paved & Miscellaneous Concrete Surfaces MA8, PF1, DB5, DB1, SS12, SS24 - Survey Design, Appendix B to Final Status Survey Report for Saxton Nuclear Experimental Corporation Residual Macadam in OL1)
• E900-05-015, Rev. 1 to Calculation E900-05-015, OL1 Paved & Miscellaneous Concrete Surfaces MA8, PF1, DB5, DB1, SS12, SS24-Survey Design, Appendices B - D to Final Status Survey Report for Saxton Nuclear Experimental Corp Residual Concrete in OL1  + (Rev. 1 to Calculation E900-05-015, OL1 Paved & Miscellaneous Concrete Surfaces MA8, PF1, DB5, DB1, SS12, SS24-Survey Design, Appendices B - D to Final Status Survey Report for Saxton Nuclear Experimental Corp Residual Concrete in OL1)
• RS-05-114, Rev. 1 to Calculation QDC-0000-M-1408, Atmospheric Dispersion Factors (X/Qs) for Accident Release  + (Rev. 1 to Calculation QDC-0000-M-1408, Atmospheric Dispersion Factors (X/Qs) for Accident Release)
• ML052430333  + (Rev. 1 to Calculation QDC-0000-N-1267, Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms)
• ML052430284  + (Rev. 1 to Calculation QDC-0000-N-1268, Re-analysis of Control Rod Drop Accident Using Alternative Source Terms)
• NG-07-0253, Rev. 1 to Core Operating Limits Report for Cycle 21 Operation  + (Rev. 1 to Core Operating Limits Report for Cycle 21 Operation)
• ML040760092  + (Rev. 1 to EPIP - 4.35)
• ML032760146  + (Rev. 1 to Emergency Plan Implementing Procedure EP-AA-110-301, Core Damage Assessment (Bwr))
• ML032790025  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element...,Table of Contents Through Entergy 08/)
• ML032790033  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachments 38-46)
• ML032790027  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix a Through Appendix C, Attac)
• CNRO-2003-00033, Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachment 47 Thr  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachment 47 Through En)
• ML032790030  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachments 14-24)
• ML032790029  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachments 2-13)
• ML032790032  + (Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachments 25-37)
• NL-09-076, Rev. 1 to Holtec Report HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center  + (Rev. 1 to Holtec Report HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center)
• ML060870132  + (Rev. 1 to Reconciliation of Program & Line Item Differences Between January 2005 Draft NUREG-1801 & September 2005 Revision 1 of NUREG-1801)
• ML12359A008  + (Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 1 of 4)
• RS-12-177, Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 4 of 4  + (Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 4 of 4)
• ML12359A005  + (Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 2 of 4)
• ML12359A006  + (Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 3 of 4)
• ML061990074  + (Rev. 1 to SG-SGDA-05-48-NP, WOG PA-MSC-0190, Revision 1: Test Results Related to Tig and Alloy 800 Sleeve Installation in 3/4 Inch and 7/8 Inch OD SG Tubing in Service Inspection Requirements)
• ML061700107  + (Rev. 1 to WCAP-16518-NP, Beaver Valley Unit 2 Spent Fuel Pool Criticality Analysis)

• RIS 2007-21, Rev. 1, Adherence to Licensed Power Limits  + (Rev. 1, Adherence to Licensed Power Limits)

• ML23243B012  + (Rev. 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactor (Pre-decisional) ACRS Version)
• ML16196A237  + (Rev. 1, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source Byproduct, & SNM)
• RIS 2005-31, Rev. 1, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source Byproduct, & SNM  + (Rev. 1, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source Byproduct, & SNM)
• RIS 2005-31, Official Exhibit - Mandatory Hearing - NRC000086-MA-BD01 - NRC Reg Issue Summary 2005-31, Control of Security-Related Sensitive Unclassified Non-Safeguards Info Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the  + (Official Exhibit - Mandatory Hearing - NRC000086-MA-BD01 - NRC Reg Issue Summary 2005-31, Control of Security-Related Sensitive Unclassified Non-Safeguards Info Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Us)
• RIS 2005-31, 2005/12/22-NRC Prefiled Exhibit Nrc000086, NRC Regulatory Issue Summary 2005-31, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the U  + (2005/12/22-NRC Prefiled Exhibit Nrc000086, NRC Regulatory Issue Summary 2005-31, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use)
• Regulatory Guide 3.40  + (Rev. 1, Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants)
• Regulatory Guide 7.10  + (Rev. 1, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material)
• Regulatory Guide 3.72  + (Rev. 1, Guidance for Implementation of 10 CFR 72.48, Changes, Tests, and Experiments)
• ML16315A130  + (Rev. 1, Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components)
• RIS 2005-27, Rev. 1, NRC Timeliness Goals, Prioritization of Incoming License Applications and Voluntary Submittal of Schedule for Future Actions for NRC Review  + (Rev. 1, NRC Timeliness Goals, Prioritization of Incoming License Applications and Voluntary Submittal of Schedule for Future Actions for NRC Review)
• ML23237B408  + (Rev. 1, Periodic Review)
• ML17256A104  + (Rev. 1, Qualification of Safety-Related Vented Lead-Acid Storage Batteries for Nuclear Power Plants)
• ML15170A003  + (Rev. 1, Sizing of Large Lead-Acid Storage Batteries)
• ML17111A699  + (Rev. 1, Training and Qualification of Security Personnel at Nuclear Power Reactor Facilities)
• ML19343C031  + (Rev. 111 to Licensee Controlled Specifications Manual - Part 1 of 2)
• ML19343C035  + (Rev. 111 to Licensee Controlled Specifications Manual - Part 2 of 2)
• ML20303A181  + (Rev. 117 to Technical Requirement Manual, Unit 1, Part 2)
• ML20303A183  + (Rev. 117 to Technical Requirements Manual, Unit 1, Part 1)
• ML091280241  + (Rev. 12 to Updated Final Safety Analysis Report, Revision 9 to Appendix R, Fire Protection Safe Shutdown Capability, Revision 10 to Appendix a, Evaluation & Comparison to BTP Apcsb 9.5-1, & Revision 112 to Technical Requirements Manual)
• ML071830122  + (Rev. 12, Transmittal of Technical Requirements Manual)
• ML18355A541  + (Rev. 120 to Technical Specifications Bases (TS Bases))
• ML20303A180  + (Rev. 123 to Technical Requirement Manual, Unit 2)
• ML21307A083  + (Rev. 128 to Technical Requirements Manual Vol. I)
• ML062440060  + (Rev. 14 to Emergency Plan for the University of Florida Training Reactor)
• ML22049A114  + (Rev. 16 to Updated Final Safety Analysis Report, Revs. 25 & 24 to Fire Protection Reports, Vol. 1 & 2)