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
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