United States Nuclear Regulatory Commission - Protecting People and the Environment

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

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

A Study of Remote Visual Methods to Detect Cracking in Reactor Components

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

October 16, 2007

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

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

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

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

September 17, 2007

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

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

September 10, 2007

FAVOR Code Versions 2.4 and 3.1 Verification and Validation Summary Report

September 10, 2007

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

September 10, 2007

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

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

July 27, 2007

Baseline Risk Index for Initiating Events (BRIIE)

Coexistence Assessment of Industrial Wireless Protocols in the Nuclear Facility Environment

July 26, 2007

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

Final Report-Assessment of Potential Phosphate Ion-Cenmentitious Materials Interactions

June 2007

June 19 , 2007

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

June 15 , 2007

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

Carolfire Test Report

May 17 , 2007

Security Spotlight

Probabilities of Failure and Uncertainty Estimate Information for Passive Components - A Literature Review

May 16 , 2007

Sensitivity Studies of Failure of Steam Generator Tubes during Main Steam Line Break and Other Secondary Side Depressurization Events

May 9 , 2007

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

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

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

March 2007

March 27 , 2007

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

March 14 , 2007

Expert Panel Report on Proactive Materials Degradation Management

March 13 , 2007

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

March 9 , 2007

Non-destructive and Failure Evaluation of Tubing from a Retired Steam Generator

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 NRC Library. 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.

Control of Heavy Loads at Nuclear Power Plants

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

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

March 6 , 2007

Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

March 1 , 2007

Software Quality Assurance Program and Guidelines

February 2007

February 28, 2007

NUREG-1307, Revision 12
Report on Waste Burial Charges

Assessment of Eddy Current Testing for the Detection of Cracks in Cast Stainless Steel Reactor Piping Components

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

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

Page Last Reviewed/Updated Thursday, August 27, 2015