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# Site Additions in 2007

On this page:
        - December
        - November
        - October
        - September
        - August
        - July
        - June
        - May
        - April
        - March
        - February
        - January

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**

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 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.

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

Page Last Reviewed/Updated Tuesday, November 9, 2021

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Page Last Reviewed/Updated Tuesday, November 9, 2021