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Previous Site Additions
2008
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Site Additions in 2007

On this page:

See also New on Our Site for current additions.

December 2007

December 27, 2007

NUREG-1855, Draft Report For Comment
Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making

December 13, 2007

NUREG-1415, Vol. 20, No. 1
Office of the Inspector General Semiannual Report to Congress

December 4, 2007

NUREG/CR-6903, Vol. 2
Human Event Repository and Analysis (HERA): The HERA Coding Manual and Quality Assurance

November 2007

November 28, 2007

NUREG-1556, Vol. 13, Rev. 1, Final Report
Program-Specific Guidance About Commercial Radiopharmacy Licenses

November 19, 2007

NUREG-6948, Vol. 1
Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Logic, Strategic Approach and Discussion

NUREG-6948, Vol. 2
Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Case Study Applications

November 15, 2007

NUREG-1542, Vol. 13
Performance and Accountability Report - Fiscal Year 2007

November 9, 2007

NUREG-1505, Rev. 1
A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys

October 2007

October 30, 2007

NUREG/BR-0204
Instructions for Completing NRC's Uniform Low-Level Radioactive Waste Manifest

October 24, 2007

NUREG-1350, Vol. 19
Information Digest, 2007-2008

October 22, 2007

NUREG/CR-6943
A Study of Remote Visual Methods to Detect Cracking in Reactor Components

NUREG-1852
Demonstrating the Feasibility and Reliability of Operator Manual Actions
in Response to Fire

October 16, 2007

NUREG/CR-6942
Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments

October 15 , 2007

NUREG-1021, Rev. 9, Supplement 1
Operator Licensing Examination Standards for Power Reactors

NUREG-1122, Rev. 2, Supplement 1
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors

NUREG-1123, Rev. 2, Supplement 1
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors

October 10, 2007

NUREG-1887
RASCAL 3.0.5: Description of Models and Methods

October 01 , 2007

NUREG/CP-0152, Vol. 6
Proceedings of the Ninth NRC/ASME Symposium on Valves, Pumps and Inservice Testing

NUREG/CR-6941
Soil-to-Plant Concentration Ratios for Assessing Food-Chain Pathways in Biosphere Models

NUREG/CR-6268, Rev. 1
Common-Cause Failure Database and Analysis System: Event Data Collection, Classification, and Coding

September 2007

September 21, 2007

NUREG-1888
Draft Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma

September 17, 2007

NUREG-1806
Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61) (NUREG-1806, Vol. 1 and Vol. 2)

September 13, 2007

NUREG-1764, Rev. 1
Guidance for the Review of Changes to Human Actions

September 11, 2007

NUREG/CR-4667, Vol. 36
Environmentally Assisted Cracking in Light Water Reactors

September 10, 2007

NUREG-1872
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site

September 10, 2007

NUREG-1795
FAVOR Code Versions 2.4 and 3.1 Verification and Validation Summary Report

September 10, 2007

NUREG/CR-6855
Fracture Analysis of Vessels - Oak Ridge FAVOR, V04.1, Computer Code: User’s Guide

September 10, 2007

NUREG/CR-6854
Fracture Analysis of Vessels - Oak Ridge FAVOR v04.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations

September 10, 2007

NUREG-0933, Supplement 31
A Prioritization of Generic Safety Issues

August 2007

August 16, 2007

NUREG-0090, Vol. 29
Report to Congress on Abnormal Occurrences - FY 2006

August 7, 2007

NUREG-1614, Strategic Plan, Vol. 4
FY 2007 - FY 2012 Strategic Plan

August 1, 2007

NUREG-1437, Supplement 30
Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Vermont Yankee Nuclear Power Station (NUREG-1437, Supplement 30) Final Report

July 2007

July 31, 2007

NUREG/CR-6940
Combined Estimation of Hydrogeologic Conceptual Model, Parameter, and Scenario Uncertainty with Application to Uranium Transport at the Hanford Site 300 Area

July 27, 2007

NUREG/CR-6932
Baseline Risk Index for Initiating Events (BRIIE)

NUREG/CR-6939
Coexistence Assessment of Industrial Wireless Protocols in the Nuclear Facility Environment

July 26, 2007

Palo Verde

NUREG/IA-0206
Simulation of the Propagation of Pressure Waves in Piping Systems with RELAP5/MOD 3.2.2, Comparison of Computed and Measured Results

July 20, 2007

NUREG-1556, Vol. 9, Rev. 2
Program - Specific Guidance About Medical Use Licenses

July 11 , 2007

NUREG/CR-6938
Final Report-Assessment of Potential Phosphate Ion-Cenmentitious Materials Interactions

June 2007

June 19 , 2007

NUREG-1807
Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1

June 15 , 2007

NUREG/IA-210
In-Tube Steam Condensation in the Presence of Air Under Transient Conditions

June 5 , 2007

NUREG/-1824, Vols. 1-7, Final Report
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications

May 2007

May 31 , 2007

NUREG/-1556, Vol. 21
Program-Specific Guidance About Possession Licenses for Production of Radioactive Material Using an Accelerator

May 30 , 2007

NUREG/CR-6931
Carolfire Test Report

May 17 , 2007

Security Spotlight

NUREG/CR-6936
Probabilities of Failure and Uncertainty Estimate Information for Passive Components - A Literature Review

May 16 , 2007

NUREG/CR-6935
Sensitivity Studies of Failure of Steam Generator Tubes during Main Steam Line Break and Other Secondary Side Depressurization Events

May 9 , 2007

NUREG/CR-6934
Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping - A Basis for Improvements to ASME Code Section XI Appendix L

April 2007

April 24 , 2007

NUREG-1864
A Pilot Probabilistic Risk Assessment Of a Dry Cask Storage System At a Nuclear Power Plant.

April 13 , 2007

Security for Radioactive Material
The NRC has posted a new series of web pages regarding the security of radioactive material

April 4 , 2007

NUREG/CR-6926
Evaluation of the Seismic Design Criteria in ASCE/SEI Standard 43-05 for Application to Nuclear Power Plants

March 2007

March 27 , 2007

NUREG-1516
Management of Radioactive Material Safety Programs at Medical Facilities - Final Report

March 14 , 2007

NUREG/CR-6923
Expert Panel Report on Proactive Materials Degradation Management

March 13 , 2007

NUREG/CR-6930
Temperature Dependence of Weibull Stress Parameters: Studies Using the Euro-Material Similar to ASME A508 Class-3 Steel

March 9 , 2007

NUREG/CR-6924
Non-destructive and Failure Evaluation of Tubing from a Retired Steam Generator

NUREG/CR-6933
Assessment of Crack Detection in Heavy-Walled Cast Stainless Steel Piping Welds Using Advanced Low-Frequency Ultrasonic Methods

March 8 , 2007

NUREG/BR-0007, Revision 6
Instructions for the Preparation and Distribution of Material Status Reports

NUREG/BR-0006, Revision 7
Instructions for Completing Nuclear Material Transaction Reports

March 7 , 2007

The NRC Documents and Publications link on the Home Page has been renamed to its former title of Electronic Reading Room. This link appears as a blue button on the left and includes a drop-down menu. This was done to alleviate users' inability to locate key information.

NUREG-0612
Control of Heavy Loads at Nuclear Power Plants

NUREG-1465
Accident Source Terms for Light-Water Nuclear Power Plants - Final Report

NUREG-1765
Basis Document for Large Early Release Frequency (LERF) Significance Determination Process (SDP) Inspection Findings that May Affect LERF

March 6 , 2007

NUREG/CR-6927
Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

March 1 , 2007

NUREG/BR-0167
Software Quality Assurance Program and Guidelines

February 2007

February 28, 2007

NUREG-1307, Revision 12
Report on Waste Burial Charges

NUREG/CR-6929
Assessment of Eddy Current Testing for the Detection of Cracks in Cast Stainless Steel Reactor Piping Components

NUREG/CR-6928
Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants

NUREG/CR-5698
Comparing Monitoring Strategies at the Maricopa Environmental Monitoring Site, Arizona

February 23, 2007

OMB Exhibit 300s

NUREG/BR-0099, Revision 12, Spent Fuel Transportation Package Response to the
Caldecott Tunnel Fire Scenario

NUREG/CR-6894, Revision 1, Spent Fuel Transportation Package Response to the
Caldecott Tunnel Fire Scenario

February 13, 2007

NUREG/CR-6917, Experimental Measurements of Pressure Drop Across Sump Screen Debris Beds in Support of Generic Safety Issue 191

February 9, 2007

NUREG/CR-6909, Final Report , Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials

February 8, 2007

NUREG-4461, Revision 2 , Tornado Climatology of the Contiguous United States

February 5, 2007

NUREG-1100, Vol. 23, Performance Budget: Fiscal Year 2008

January 2007

January 30, 2007

NUREG-1814, Status of the Decommissioning Program - 2006 Annual Report

January 26, 2007

NUREG-1853, History and Framework of Commercial Low-Level Radioactive Waste Management in the United States

Digital Instrumentation and Controls (I&C)

January 25, 2007

NUREG/CR-6922, P-CARES: Probabilistic Computer Analysis for Rapid Evaluation of Structures

January 24, 2007

NUREG/CR-6925, Assessment of Analysis Methods for Seismic Shear Wall Capacity Using JNES/NUPEC Multi-Axial Cyclic and Shaking Table Test Data

NUREG/CR-6082, Data Communications

NUREG/CR-6083, Reviewing Real-Time Performance of Nuclear Reactor Safety Systems

NUREG/CR-6090, The Programmable Logic Controller and Its Application in Nuclear Reactor Systems

NUREG/CR-6421, A Proposed Acceptance Process for Commercial Off-the-Shelf (COTS) Software in Reactor Applications

January 23, 2007

NUREG-0713, Vol. 27, Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2005

January 16, 2007

NUREG-1575, Supplement 1, Multi-Agency Radiation Survey and Assessment of Materials and Equipment Manual (MARSAME) - Draft Report for Comment

January 9, 2007

NUREG/CR-6914, Integrated Chemical Effects Test Project



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