| Documents added January 1, 2000 through May 5, 2007 |
| V = Volume | N = Number | R =Revision | P = Part | S = Supplement | Ch = Chapter | Add = Addendum | Sec = Section | DFC = Draft For Comment |
PUBLICATION
NUMBER |
TITLE |
DATE OF
PUBLICATION |
ADAMS
ACCESSION
NUMBER |
NUREG-1437 S32 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants:
Regarding Wolf Creek Generating Station (Final Report) |
May 2008 |
ML081260608 |
NUREG/CR-6931 V1 |
Cable Response to Live Fire (CAROLFIRE): Test Descriptions
and Analysis of Circuit Response Data |
April 2008 |
ML081190230 |
NUREG/CR-6931 V2 |
Cable Response to Live Fire (CAROLFIRE): Cable Fire Response
Data for Fire Model Improvement |
April 2008 |
ML081190248 |
NUREG/CR-6931 V3 |
Cable Response to Live Fire (CAROLFIRE): Thermally-Induced
Electrical Failure (THIEF) Data |
April 2008 |
ML081190261 |
NUREG/CR-9645 |
Fabrication Flaw and Distribution In Repairs to Reactor
Pressure Vessel and Piping Welds |
April 2008 |
ML081130470 |
NUREG/CR-6959 |
Application of Surface Complexation Modeling to Selected Radionuclides and Aquifer
Sediments |
April 2008 |
ML081190302 |
NUREG-1437 S35 DFC |
Generic Environmental Impact
Statement for the License Renewal of
Nuclear Plants: Regarding Susquehanna Steam Electric Station, Units 1 & 2
(Report for Comment) |
April 2008 |
ML081140337 |
NUREG-1437 S34 DFC |
Generic Environmental Impact
Statement for the License Renewal of
Nuclear Plants: Regarding Vogtle Electric
Generating Plant, Units 1 & 2 (Draft Report for Comment) |
April 2008 |
ML081080299 |
NUREG/CR-6944 V1 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): Main Report |
March 2008 |
ML081140459 |
NUREG/CR-6944 V2 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): Accidents and Thermal Fluids Analysis PIRTs |
March 2008 |
ML081140460 |
NUREG/CR-6944 V3 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): |
March 2008 |
ML081140461 |
NUREG/CR-6944 V4 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): |
March 2008 |
ML081140462 |
NUREG/CR-6944 V5 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): |
March 2008 |
ML081140463 |
NUREG/CR-6944 V6 |
Next Generation Nuclear Plant Phenomena Identification and
Ranking Tables (PIRTS): Process Heat and Hydrogen Co-Generation PIRTs |
March 2008 |
ML081140464 |
NUREG/CR-6960 |
Crack Growth Rates and Fracture Toughness of Irradiated Austenitic
Stainless Steels in BWR Environments |
March 2008 |
ML081130709 |
NUREG/CR-6957 |
Correlation Analysis of JNES Seismic Wall Pressure Data
for ABWR Model Structures |
March 2008 |
ML080940428 |
| NUREG-1830 V4 |
Office of Investigations Annual Report FY-2007 |
Feb 2008 |
ML080510514 |
| NUREG/CR-6956 |
Nonlinear Analyses for Embedded Cracks Under pressurized Thermal Shock: Comparisons with FAVOR and Weibull Stress Approaches |
Feb 2008 |
ML080500276 |
| NUREG-1542 V13 S1 |
Performance and Accountability Report Highlights FY-2007 |
Feb 2008 |
ML080100209 |
| NUREG-1556 V9 R2 |
Consolidated Guidance About
Material Licenses: Program-Specific
Guidance About Medical Use Licenses (Final) |
Jan 2008 |
ML073400289 |
| NUREG/CR-6955 |
Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask |
Jan 2008 |
ML080580257 |
| NUREG-1437 S31 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding James A. FitzPatrick Nuclear Power Plant (Final) |
Jan 2008 |
ML080170183 |
| NUREG/CR-6951 |
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit |
Dec 2007 |
ML080701107 |
| NUREG-1860 V1 |
Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing – Main Report |
Dec 2007 |
ML080440170 |
| NUREG-1860 V2 |
Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing – Appendices A-L |
Dec 2007 |
ML080440215 |
| NUREG/CR-6953 V1 |
Review of NUREG-0654, Supplement 3, "Criteria for Protective Action Recommendations for Severe Accidents" |
Dec 2007 |
ML080360602 |
| NUREG/CR-6949 |
The Employment of Empirical Data and Bayesian Methods in Human Reliability Analysis: A Feasibility Study |
Dec 2007 |
ML080230610 |
| NUREG-0713 V28 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2006 - 39th Annual Report |
Dec 2007 |
ML080100423 |
| NUREG-1873 |
Environmental Impact Statement (EIS) for the License Renewal of the National Bureau of Standards Reactor (Final Report) |
Dec 2007 |
ML073620086 |
| NUREG-1437 S33 DFC |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Shearon Harris Nuclear Power Plant, Unit 1 (Draft for Comment) |
Dec 2007 |
ML073320364 |
| NUREG-1574 R2 |
Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforcement |
Dec 2007 |
ML073410572 |
| NUREG-1542 V13 |
Performance and Accountability Report FY 2007 |
Nov 2007 |
ML080100199 |
| NUREG-1855 DFC |
Guidance on the Treatment of Uncertainties Associated with PRA's in Risk-Informed Decision Making (Draft For Comment) |
Nov 2007 |
ML080040199 |
| NUREG/CR-6903 V2 |
Human Event Repository and Analysis (HERA): The HERA Coding Manual and Quality Assurance |
Nov 2007 |
ML073470315 |
| NUREG/CR-6948 V1 |
Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Logic, Strategic Approach and Discussion |
Nov 2007 |
ML073310297 |
| NUREG/CR-6948 V2 |
Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Case Study Applications |
Nov 2007 |
ML073320395 |
| NUREG-1891 |
Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station |
Nov 2007 |
ML073241016 |
| NUREG-1556 V13 R1 |
Consolidated Guidance About Material Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses (Final Report) |
Nov 2007 |
ML073180179 |
| NUREG/CR-6943 |
A Study of Remote Visual Methods to Detect Cracking in Reactor Components |
Oct 2007 |
ML073110060 |
| NUREG/CR-6942 |
Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments |
Oct 2007 |
ML073030092 |
| NUREG-1021 R1 S1 |
Operator Licensing Examination Standards for Power Reactors -- Final Report |
Oct 2007 |
ML072970315 |
| NUREG-1122 R2 S1 |
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors – Final Report |
Oct 2007 |
ML072970334 |
| NUREG-1123 R2 S1 |
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors – Final Report |
Oct 2007 |
ML072970322 |
| NUREG/BR-0238 R15 |
Materials Annual Fee Billing Handbook |
Oct 2007 |
ML072690040 |
| NUREG-1556 V21 |
Consolidated Guidance About Material Licenses: Program-Specific Guidance About Possession Licenses for Production of Radioactive Material Using an Accelerator |
Oct 2007 |
ML072900058 |
| NUREG-1852 |
Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire |
Oct 2007 |
ML073020676 |
| NUREG/IA-0215 |
Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR |
Sept 2007 |
ML073380691 |
| NUREG-1650 R2 |
The United States of America Fourth National Report for the Convention on Nuclear Safety |
Sept 2007 |
ML073110536 |
| NUREG-1889 |
RASCAL 3.0.5 Workbook |
Sept 2007 |
ML072970068 |
| NUREG/CR-6268 R1 |
Common-Cause Failure Database ad Analysis System: Event Data Collection, Classification, and Coding |
Sept 2007 |
ML072970404 |
| NUREG/BR-0050 R5 |
ACNW & M FY2007 – FY2008 Action Plan |
Sept 2007 |
ML072850216 |
| NUREG-1885 |
Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category 1 Fuel Cycle Facilities: Results and Status Update |
Sept 2007 |
ML072640242 |
| NUREG-1888 DFC |
Generic Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma (Draft for Comment) |
Sept 2007 |
ML072570039 |
| NUREG-1764 R1 |
Guidance for the Review of Changes to Human Actions |
Sept 2007 |
ML072640413 |
| NUREG-1437 S32 DFC |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Wolf Creek Generating Station (Draft for Comment) |
Sept 2007 |
ML072540026 |
| NUREG‑1872 V1 DFC |
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site -- Main Report (Draft for Comment) |
Sept 2007 |
ML072410045 |
| NUREG‑1872 V2 DFC |
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site – Appendices (Draft for Comment) |
Sept 2007 |
ML072410049 |
| NUREG/CR-4667 V36w/Errata |
Environmentally Assisted Cracking in Light Water Reactors – Annual Report 2005 (Errata issued for pages 45 and 48 has been incorporated into document) |
Aug 2007 |
ML073120263 |
| NUREG-1350 V19 |
USNRC Information Digest 2007-2008 |
Aug 2007 |
ML072960367 |
| NUREG/CR-6941 |
Soil-to-Plant Concentration Ratios for Assessing Food Chain Pathways in Biosphere Models |
Aug 2007 |
ML072780220 |
| NUREG-1806 V1 |
Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50,61) - Main Report |
Aug 2007 |
ML072830074 |
| NUREG-1806 V2 |
Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50,61) - Appendices |
Aug 2007 |
ML072820691 |
| NUREG-1795 |
FAVOR Code Versions 2.3 and 3.1 Verification and Validation Summary Report |
Aug 2007 |
ML072820045 |
| NUREG/CR-6954 |
Fracture Analysis of Vessels – Oak Ridge FAVOR, v04.1, Computer Code User's Guide |
Aug 2007 |
ML072840547 |
| NUREG/CR-6955 |
Fracture Analysis of Vessels – Oak Ridge FAVOR, v04.1, Computer Code User's Guide |
Aug 2007 |
ML072760089 |
| NUREG/CP-0152 V6 |
Proceedings of the Ninth NRC/ASME Symposium on Valves, Pumps and Inservice Testing – July 17-19, 2006 |
Aug 2007 |
ML072700042 |
| NUREG-1887 |
RASCAL 3.0.5: Description of Models and Methods |
Aug 2007 |
ML072480633 |
| NUREG-1854 |
NRC Staff Guidance for Activities Related to U.S.
Department of Energy Waste Determinations - Draft Final Report for Interim Use |
Aug 2007 |
ML072360184 |
| NUREG-1841 |
U.S. Operating Experience with Thermally Treated Alloy 690 Steam Generator Tubes |
Aug 2007 |
ML072330588 |
| NUREG-0933 S31 |
A Prioritization of Generic Safety Issues |
July 2007 |
ML080710250 |
| NUREG-0936 V26 N1 |
NRC Regulatory Agenda Semiannual Report Jan - June 2007 |
July 2007 |
ML072360180 |
| NUREG/BR-0117 #07-02 |
NMSS Licensee Newsletter |
July 2007 |
ML072330088 |
| NUREG/CR-6940 |
Combined Estimation of Hydrogeologic Conceptual Model, Parameter, and Scenario Uncertainty with Applications to Uranium Transport at the Hanford Site 300 Area |
July 2007 |
ML072330538 |
| NUREG/CR-6939 |
Consistence Assessment of Industrial Wireless Protocols in the Nuclear Facility Environment |
July 2007 |
ML072210179 |
| NUREG‑1437 S30 V1 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Vermont Yankee Nuclear Power Station - Main Report |
July 2007 |
ML072050012 |
| NUREG-1437 S30 V2 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Vermont Yankee Nuclear Power Station - Appendices |
July 20007 |
ML072050013 |
| NUREG‑1437 S29 V1 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Pilgrim Nuclear Plant Station - Main Report |
July 2007 |
ML071990020 |
| NUREG-1437 S29 V2 |
Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Pilgrim Nuclear Plant Station - Appendices |
July 20007 |
ML071990027 |
| NUREG-1556 V9 R2 DFC |
Consolidated Guidance About Material Licenses: Program-Specific Guidance About Medical Use Licenses (Draft For Comment) |
July 2007 |
ML071860070 |
| NUREG-1125 V28 |
A Compilation of Reports of The Advisory Committee on Reactor
Safeguards: 2006 Annual |
June 2007 |
ML072210749 |
| NUREG/CR-6938 |
Assessment of Potential Phosphate Ion-Cementitious Materials Interactions -
Final Report |
June 2007 |
ML072200039 |
| NUREG/CR-6932 |
Baseline Risk Index Initiating Events (BRIIE) |
June 2007 |
ML072080252 |
| NUREG-1880 |
ATHEANA User's Guide |
June 2007 |
ML072130359 |
| NUREG-1807 |
Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty
Treatment Used in FAVOR Version 04.1 |
June 2007 |
ML072010411 |
| NUREG-1478 R2 |
Operator Licensing Examiner Standards for Research and Test Reactors |
June 2007 |
ML072000059 |
| NUREG/IA-0206 |
Simulation of the Propagation of Pressure Waves in Piping Systems with
RELAP/MOD 3.2.2 Comparison of Computed and Measured Results |
June 2007 |
ML071930551 |
| NUREG-1873 DFC |
Draft Environmental Impact Statement (DEIS) for the License Renewal of
the National Bureau of Standards Reactor (Draft for Comment0 |
June 2007 |
ML072140496 |
| NUREG-1556 V13 R1
DFC |
Consolidated Guidance About Material Licenses: Program-Specific
Guidance About Commercial Radiopharmacy Licenses (Draft For Comment) |
June 2007 |
ML071581047 |
| NUREG-1437 S31 DFC |
Generic Environmental Impact Statement for the License Renewal of
Nuclear Plants: Regarding James A. FitzPatrick Nuclear Power Plant (Draft
for Comment) |
June 2007 |
ML071420019 |
| NUREG/IA-0210 |
In-Tube Steam Condensation In The Presence of Air Under Transient
Conditions |
May 2007 |
ML072070054 |
| NUREG-1824 V1 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Main Report |
May 2007 |
ML071650546 |
| NUREG-1824 V2 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Experimental Uncertainty |
May 2007 |
ML071730305 |
| NUREG-1824 V3 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire Dynamic Tools |
May 2007 |
ML071730493 |
| NUREG-1824 V4 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire Induced Vulnerability |
May 2007 |
ML071730499 |
| NUREG-1824 V5 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Consolidated Fire Growth...... |
May 2007 |
ML071730527 |
| NUREG-1824 V6 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: MAGIC |
May 2007 |
ML071730504 |
| NUREG-1824 V7 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire Dynamic Simulator |
May 2007 |
ML071730543 |
| NUREG/CR-6934 |
Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping |
May 2007 |
ML071760205 |
| NUREG-1021 R9 S1
DFC |
Operator Licensing Examination Standards for Power Reactors (Draft For
Comment) |
May 2007 |
ML071580694 |
| NUREG-1122 R2 S1
DFC |
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling
Water Reactors (Draft for Comment) |
May 2007 |
ML071580631 |
| NUREG-1123 R2 S1
DFC |
Knowledge and Abilities Catalog for Nuclear Power Plant Operators:
Pressurized Water Reactors (Draft for Comment) |
May 2007 |
ML071580691 |
| NUREG-1556 V21 DFC |
Consolidated Guidance About Material Licenses: Program-Specific
Guidance About Possession Licenses for Production of Radioactive
Materials Using An Accelerator (Draft For Comment) |
May 2007 |
ML071500523 |
| NUREG/CR-6936 |
Probabilities of Failure and Uncertainty Estimate Information for Passive
Components - A Literature Review |
May 2007 |
ML071430371 |
| NUREG/CR-6935 |
Sensitivity Studies of Failure of Steam Generator Tubes During Main Steam
Line Break and Other Secondary Side Depressurization Events |
May 2007 |
ML071430396 |
| NUREG-1875 V1 |
Safety Evaluation Report Relating to the License Renewal of Oyster Creek
Generating Station |
April 2007 |
ML071290023 |
| NUREG-1875 V2 |
Safety Evaluation Report Relating to the License Renewal of Oyster Creek
Generating Station |
April 2007 |
ML071310246 |
| NUREG/IA-0204 |
OLKILUOTO 2 - RELAP5//MOD 3.2.1.2: Analysis of the Reactor Scram on
June 13, 1997 |
April 2007 |
ML071290556 |
| NUREG-0090 V29 |
Report to Congress on Abnormal Occurrences - Fiscal Year 2006 |
April 2007 |
ML071080195 |
| NUREG-1864 |
A Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear
Power Plant |
March 2007 |
ML071340012 |
| NUREG/CR-6933 |
Assessment of Crack Detection in Heavy-Walled Cast Stainless Steel Piping
Welds Using Advanced Low-Frequency Ultrasonic Methods |
March 2007 |
ML071020409 |
| NUREG/CR-6924 |
Non-Destructive and Failure Evaluation of Tubing Steam Generator |
March 2007 |
ML070950140 |
| NUREG/BR-0164 R5 |
NRC - Regulators of Nuclear Safety |
March 2007 |
ML071020089 |
| NUREG/CR-6930 |
Temperature Dependence of Weibull Stress Parameters: Studies Using the
Euro-Material Similar to ASME A508 Class-3 Steel |
March 2007 |
ML070810521 |
| NUREG/CR-6917 |
Experimental Measurement of Pressure Drop Across Sump Screen Debris
Beds in Support of GSI-191 |
Feb 2007 |
ML071910178 |
| NUREG-1862 |
Development of a Pressure Drop Calculation Method for Debris-Covered
Sump Screens in Support of Generic safety issue 191 |
Feb 2007 |
ML071520440 |
| NUREG/CR-6927 |
Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures
- A Review of Pertinent Factors |
Feb 2007 |
ML070850183 |
| NUREG/CR-4461 R2 |
Tornado Climatology of the Contiguous United States |
Feb 2007 |
ML070810400 |
| NUREG-1574 R2 DFC |
Standard review Plan on Transfer and Amendment of Antitrust License
Condition and Antitrust Enforcement |
Feb 2007 |
ML070160586 |
| NUREG-0936 V25 N2 |
NRC Regulatory Agenda Semiannual Report July - December 2006 |
Feb 2007 |
ML070740647 |
| NUREG/BR-0007 R6
DFC |
Instruction for the Preparation and Distribution of Material Status Reports
(DOE/NRC Forms 742 and 742C) |
Feb 2007 |
ML070750363 |
| NUREG/BR-0006 R7
DFC |
Instructions for Completing Nuclear Material Transaction Reports
(DOE/NRC Forms 741 and 740M |
Feb 2007 |
ML070750371 |
| NUREG/CR-6929 |
Assessments of Eddy Currents Testing for the Detection of Cracks in Cast
Stainless Steel Reactor Piping Components |
Feb 2007 |
ML070670477 |
| NUREG/CR-6923 |
Expert Panel Report on Proactive Materials Degradation Assessments |
Feb 2007 |
ML070710255 |
| NUREG/CR-6923 |
Expert Panel Report on Proactive Materials Degradation Assessments;
Appendices D, E, and F |
Feb 2007 |
ML070930117 |
| NUREG/CR-6909 |
Effects of LWR Coolant Environments on the Fatigue Life of Reactor
Materials - Final Report |
Feb 2007 |
ML070660620 |
| NUREG/BR-0099 R12 |
The United States Nuclear Regulatory Commission |
Feb 2007 |
ML070460435 |
| NUREG-1830 V3 |
Office of Investigations Annual Report FY2006 |
Feb 2007 |
ML070460329 |
| NUREG/BR-0332 |
U.S. Nuclear Regulatory Commission Training and Development Strategic Plan: Safety
Through Knowledge |
Feb 2007 |
ML070370271 |
| NUREG-1814 R1 |
Status of the Decommissioning Program - 2006 Annual Report |
Feb 2007 |
ML070600680 |
| NUREG/CR-6925 |
Assessment of Analysis Methods for Seismic Shear Wall Capacity Using
JNES/NUPEC Multi-Axial Cyclic and Shaking Table Test Data |
Jan 2007 |
ML071900254 |
| NUREG/CR-6922 |
P-CARES: Probabilistic Computer Analysis for Rapid Evaluation of
Structures |
Jan 2007 |
ML070850261 |
| NUREG-1853 |
History and Framework of Commercial Low-Level Radioactive Waste
Management in the United States - ACNW White Paper |
Jan 2007 |
ML070600684 |
| NUREG-1871 |
Safety Evaluation Report Related to the License Renewal of Palisades
Nuclear Plant |
Jan 2007 |
ML070600578 |
| NUREG/CR-6894 R1 |
Spent Fuel Transportation Package Response to the Caldecott Tunnel Fire
Scenario |
Jan 2007 |
ML070460351 |
| NUREG/CR-6870 |
Consideration of Geochemical Issues in Groundwater Restoration at Uranium
In-Situ Leach Mining Facilities |
Jan 2007 |
ML070600405 |
| NUREG-1437 S28 V2 |
Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding
Oyster Creek Nuclear Generating Station, Appendices - Final |
Jan 2007 |
ML070100258 |
| NUREG-1437 S28 V1 |
Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding
Oyster Creek Nuclear Generating Station, Main Report - Final |
Jan 2007 |
ML070100234
|
| NUREG/CR-6912 |
GSI-191 PWR Sump Screen Blockage Chemical Effects Tests:
Thermodynamic Simulations |
Dec 2006 |
ML071900449 |
| NUREG/CR-6914 V1 |
Integrated Chemical Effects Test Project: Consolidated Data Report |
Dec 2006 |
ML071800321 |
| NUREG/CR-6914 V2 |
Integrated Chemical Effects Test Project: Test #1 Data Report |
Dec 2006 |
ML072260402 |
| NUREG/CR-6914 V3 |
Integrated Chemical Effects Test Project: Test #2 Data Report |
Dec 2006 |
ML072260423 |
| NUREG/CR-6914 V4 |
Integrated Chemical Effects Test Project: Test #3 Data Report |
Dec 2006 |
ML072260523 |
| NUREG/CR-6914 V5 |
Integrated Chemical Effects Test Project: Test #4 Data Report |
Dec 2006 |
ML071900385 |
| NUREG/CR-6914 V6 |
Integrated Chemical Effects Test Project: Test #5 Data Report |
Dec 2006 |
ML072050297 |
| NUREG-0713 V27 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other
Facilities 2004 - 38th Annual Report |
Dec 2006 |
ML070600506 |
| NUREG/CR-6916 |
Hydraulic Transport of Coating Debris: A Subtask of GSI-191 |
Dec 2006 |
ML070220061 |
| NUREG/CR-6884 |
Model Abstraction Techniques for Soil-Water Flow and Transport |
Dec 2006 |
ML070290073 |
| NUREG-1575 S1 DFC |
Multi-Agency Radiation Survey and Assessment of Materials and Equipment Manual
(MARSAME) Draft Report for Comment |
Dec 2006 |
ML070110228 |
| NUREG/CR-6915 |
Aluminum Chemistry in a Prototypical Post-Lost-of-Coolant Accident, Pressurized-Water Containment Environment |
Dec 2006 |
ML070160448 |
| NUREG/CR-6913 |
Chemical Effects Head-Loss Research in Support of Generic Safety Issue 191 |
Dec 2006 |
ML070090549 |
| NUREG-1861 |
Peer Review of GSI-191 Chemical Effects Research Program |
Dec 2006 |
ML063630498 |
| NUREG-0383 V3 R23 |
Directory of Certificates of Compliance for Radioactive Materials Packages: Report of
NRC-Approved Quality Assurance Programs for Radioactive Materials Packages |
Dec 2006 |
ML063560385 |
| NUREG-0383 V2 R26 |
Directory of Certificates of Compliance for Radioactive Materials Packages: Certificates
of Compliance |
Dec 2006 |
ML070030458 |
| NUREG-1437 S30 DFC |
"Generic Environmental Impact Statement for License Renewal of Nuclear Plants
Regarding Vermont Yankee Nuclear Power Station" Draft for Comment |
Dec 2006 |
ML063390344 |
| NUREG-1437 S29 |
Generic Environmental Impact Statement for License Renewal of Nuclear Plants
Regarding Pilgrim Nuclear Power Station |
Dec 2006 |
ML063260173 |
| NUREG/BR-0108 R1 |
Radioactive Scrap - Be Aware! English and Spanish Versions
(Hi-Res Poster 32" x 24") |
Nov 2006 |
ML070790415 |
| NUREG/BR-0108 R1 |
Radioactive Scrap - Be Aware! English and Spanish Versions
(Low-Res Poster 17" x 11") |
Nov 2006 |
ML071080173 |
NUREG-0980 V1 N7 R1
Errata |
Nuclear Regulation Legislation; 109th Congress; 2nd Session |
Nov 2006 |
ML063630359 |
| NUREG/CR-6921 |
Crack Growth Rates in a PWR Environment of Nickel Alloys from the Davis-Besse and V. C. Summer Power Plants |
Nov 2006 |
ML063520364 |
| NUREG/CR-4667 35 |
Environmentally Assisted Cracking in Light Water Reactors: Annual Report Jan - Dec 2004 |
Nov 2006 |
ML063400384 |
| NUREG/CR-6886 R1 |
Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario (Final Report) |
Nov 2006 |
ML063350502 |
| NUREG/CR-6919 |
Recommendations for Revisions of Damping Valves in Regulatory Guide 1.61 |
Nov 2006 |
ML063260342 |
| NUREG-1835 S1 |
Safety Evaluation Report for an Early Site Permit (ESP) at an North Anna ESP Site |
Nov 2006 |
ML063170371 |
| NUREG-1542 V12 |
Performance and Accountability Report - Fiscal Year 2006 |
Nov 2006 |
ML063200026 |
| NUREG-1423 V15 |
A Compilation of Reports Advisory Committee on Nuclear Waste: September 2004 - June 2006 |
Oct 2006 |
ML063400410 |
| NUREG/CR-6918 |
VARSKIN 3: A Computer Code for Assessing Skin Dose From Skin Contamination |
Oct 2006 |
ML063320348 |
| NUREG-1836 DFC |
Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Approval of the License Termination Plan |
Oct 2006 |
ML063170151 |
| NUREG-1865 |
Safety Evaluation Report to the License Renewal of the Monticello Nuclear Generating Station |
Oct 2006 |
ML063050414 |
| NUREG-1842 |
Evaluation of Human Reliability Analysis Methods Against Good Practices (Final) |
Sept 2006 |
ML063200058 |
| NUREG-1757 V1 R2 |
Consolidated Decommissioning Guidance: Decommissioning Process for Material Licensees: Final Report |
Sept 2006 |
ML063000243 |
| NUREG-1757 V2 R1 |
Consolidated Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria: Final Report |
Sept 2006 |
ML063000252 |
| NUREG-1852 DFC |
Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire |
Sept 2006 |
ML062970251 |
| NUREG-1863 |
Review of Responses to NRC Bulletin 2003-02: Leakage From Reactor
Pressure Vessel Lower Head Penetration and Reactor Coolant Boundary Integrity Applicable to PWR Vessels |
Sept 2006 |
ML062970288 |
| NUREG-0725 R14 |
Public Information Circular for Shipment of Irradiated Reactor Fuel |
Sept 2006 |
ML062910052 |
| NUREG-1900 V1 |
Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 & 2 |
Sept 2006 |
ML062890129 |
| NUREG-1900 V2 |
Safety Evaluation Report Related to the License Renewal of Nine Mile Point
Nuclear Station, Units 1 & 2 |
Sept 2006 |
ML062890236 |
| NUREG/BR-0117 #03-06 |
NMSS Licensee Newsletter |
Sept 2006 |
ML062770040 |
| NUREG-1851 |
Safety Evaluation Report for the American Centrifuge Plant in Piketon Ohio |
Sept 2006 |
ML062700087 |
| NUREG-0800 Sec 13.3 DFC |
Standard Review Plan: Emergency Planning (Draft for Comment) |
Sept 2006 |
ML062550293 |
| NUREG/CR-6903 V1 |
Human Event Repository and Analysis System, An Overview |
Aug 2006 |
ML062700593 |
| NUREG-1350 V18 |
Information Digest: 2006-2007 Edition |
Aug 2006 |
ML062550373 |
| NUREG-0936 V25 V1 |
NRC Regulatory Agenda Semiannual Report Jan - June 2006 |
Aug 2006 |
ML062490216 |
| NUREG/CR-6906 |
Containment Integrity Research at Sandia National Laboratories: An
Overview |
Aug 2006 |
ML062440075 |
| NUREG/CR-6911 |
Tests of Uranium (IV) Adsorption in a Field Setting |
Aug 2006 |
ML062440070 |
| NUREG-0800 Sec 14.2.1 |
Standard Review Plan Generic Guidelines for Extended Power Uprate Testing
Programs |
Aug 2006 |
ML062210398 |
| NUREG-0933 S30 |
A Prioritization of Generic Safety Issues |
July 2006 |
ML070600781 |
| NUREG/BR-0147 R2 |
Fraud Awareness |
July 2006 |
ML062700084 |
| NUREG/CR-6909 DFC |
Effect of LWR Coolant Environments on Fatigue Life of Reactor Materials (Draft for Comment) |
July 2006 |
ML061650347 |
| NUREG/CR-6882 |
Assessment of Wireless Technologies and Their Applications at Nuclear Power Facilities |
July 2006 |
ML062140045 |
| NUREG-1815 V1 |
Environmental Impact Statement for an Early Site Permit (ESP) at the Exelon ESP Site: Main Report (Final) |
July 2006 |
ML061930264 |
| NUREG-1815 V2 |
Environmental Impact Statement for an Early Site Permit (ESP) at the Exelon ESP Site: Appendices A-K (Final) |
July 2006 |
ML061930275 |
| NUREG-1811 S1 DFC |
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the North Anna ESP Site |
July 2006 |
ML061800217 |
| NUREG/CR-6910 |
Alternative Conceptual Models for Assessing Food Chain Pathways in Biosphere Models |
June 2006 |
ML062210427 |
| NUREG-1125 V27 |
A Compilation of Reports of the Advisory Committee on Reactor Safeguards: 2005 Annual |
June 2006 |
ML061780504 |
| NUREG-1856 |
Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 & 2 |
June 2006 |
ML061730126 |
| NUREG/CR-6907 |
Crack Growth Rate of a Nickle Alloy Welds in a PWR Environment |
June 2006 |
ML061720302 |
| NUREG/CR-4667 V34 |
Environmentally Assisted Cracking in Light Water Reactors: Annual Report 2003 |
June 2006 |
ML061720353 |
| NUREG/BR-0224 R1 |
Guidelines for Conducting Public Meetings |
June 2006 |
ML061710199 |
| NUREG/CR-6904 |
Evaluation of the Broadband Impedance Spectroscopy Prognostic/Diagnostic
Technique for Electric Cables Used In Nuclear Power Plants |
June 2006 |
ML061670054 |
| NUREG-0980 V1 N7 R1 |
Nuclear Regulatory Legislation: 109th Congress, 2nd Session |
June 2006 |
ML061800237 |
| NUREG-1437 S28 DFC |
Generic Environmental Impact Statement for the License Renewal of Nuclear
Plants: Regarding Oyster Creek Nuclear Generating Station (Draft for Comment) |
June 2006 |
ML061520231 |
| NUREG-1854 DFC |
Standard Review Plan for Activities Related to U.S. Department of Energy
Waste Determinations - Draft Report for Interim Use and Comment |
May 2006 |
ML061520469 |
| NUREG-1635 V7 |
Review and Evaluation of the Nuclear Regulatory Commission Safety
Research Program: A Report to the U.S. Nuclear Regulatory Commission |
May 2006 |
ML061460401 |
| NUREG/CR-6905 |
Report of Experimental Results for the International Fire Model
Benchmarking and Validation Exercise #3 |
May 2006 |
ML061450207 |
| NUREG-1437 S24 |
Generic Environmental Impact Statement for the License Renewal of Nuclear
Plants: Regarding Nine Mile Point Nuclear Station , Units 1 & 2 (Final Report) |
May 2006 |
ML061290310 |
| NUREG/IA-0213 V1 |
Experimental Study of Narrow Pulse Effects on the Behavior of High Burnup
Fuel Rods with Zr-1%Nb Cladding and UO2 Fuel (VVER Type) under
Reactivity-Initiated Accident Conditions: Program Approach and Analysis of Results |
May 2006 |
ML061250211 |
| NUREG-1843 S1 |
Safety Evaluation Report Related to the License Renewal of Browns Ferry
Nuclear Plant, Units 1, 2, and 3 |
May 2006 |
ML061220272 |
| NUREG-1844 |
Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC, (EGC) ESP Site |
May 2006 |
ML061210203 |
| NUREG-1834 V1 |
Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon Ohio: Main Report |
April 2006 |
ML061250131 |
| NUREG-1834 V2 |
Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon Ohio: Appendices A thru K |
April 2006 |
ML061250101 |
| NUREG-1850 |
Frequently Asked Questions on License Renewal of Nuclear Power Reactors |
April 2006 |
ML061110022 |
| NUREG-1842 DFC |
Evaluation of Human Reliability Analysis Methods Against Good Practices (Draft for Comment) |
April 2006 |
ML061100368 |
| NUREG-1840 |
Safety Evaluation Report for an Early Site Permit (ESP) at the Grand Golf Site |
April 2006 |
ML061070443 |
| NUREG-1843 |
Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 |
April 2006 |
ML061030027 |
| NUREG-1437 S25 |
Generic Environmental Impact Statement for the License Renewal of Nuclear
Plants: Regarding Brunswick Steam Electric Plant, Units 1 & 2 (Final Report) |
April 2006 |
ML060900480 |
| NUREG-1817 |
Environmental Impact Statement for an Early Site Permit (ESP) at the Grand Golf ESP Site (Final Report) |
April 2006 |
ML060900037 |
| NUREG-0090 V28 |
Report to Congress on Abnormal Occurrences Fiscal Year 2005 |
March 2006 |
ML061170171 |
| NUREG/CR-6900 |
The Effect of Elevated Temperature on Concrete Materials and Structures - A Literature Review |
March 2006 |
ML060970563 |
| NUREG/CR-6902 |
Effects of Insulation Debris on Throttle-Valve Performance: A Subtask GSI-191 |
March 2006 |
ML061020273 |
| NUREG/IA-0213 V2 |
Experimental Study of Narrow Pulse Effects on the Behavior of High Burnup
Fuel Rods with Zr-1% Cladding and UO2 Fuel (VVER Type) Under
Reactivity- Initiated Accident Conditions: Test Conditions and Results |
March 2006 |
ML060200358 |
| NUREG/CP-0193 |
Proceedings of the International Workshop on Conceptual Model
Development for Subsurface Reactive Transport Modeling of Inorganic
Contaminants, Radionuclides, and Nutrients |
March 2006 |
ML061310013 |
| NUREG/CR-6893 |
Modeling Adsorption Process: Issues in Uncertainty, Scaling, and Prediction |
Feb 2006 |
ML061000535 |
| NUREG/CR-6898 |
A Combined Analytical Study to Characterize Uranium Soil and Sediment
Contamination: The Case of the Naturita UMTRA Site and the Role of Grain
Coatings |
Feb 2006 |
ML061020245 |
| NUREG-1609 S2 |
Standard Review Plan for Transportation Packages for Irradiated Tritium-Producing Burnable Absorber Rods (TPBARs) |
Feb 2006 |
ML060820080 |
| NUREG/CR-6896 |
Assessment of Seismic Analysis Methodologies for Deeply Embedded Nuclear Power Plant Structures |
Feb 2006 |
ML060820521 |
| NUREG/BR-0233 |
Radiation Protection and the NRC |
Feb 2006 |
ML060810112 |
| NUREG/CR-6901 |
Current State of Reliability Modeling Methodologies for Digital Systems and
Their Acceptance Criteria for Nuclear Power Plant Assessments |
Feb 2006 |
ML060800179 |
| NUREG-1437 S27 DFC |
Generic Environmental Impact Statement for the License Renewal of Nuclear
Plants: Regarding Palisades Nuclear Plant (Draft for Comment) |
Feb 2006 |
ML060400430 |
| NUREG/CR-6894 DFC |
Spent Fuel Transportation Package Response to the Caldecott Tunnel Fire Scenario |
Feb 2006 |
ML060520497 |
| NUREG-1100 V22 |
Performance Budget: Fiscal Year 2007 |
Feb 2006 |
ML060380053 |
| NUREG-0936 V24 N2 |
NRC Regulatory Agenda: Semiannual Agenda July - December 2005 |
Jan 2006 |
ML061210183 |
| NUREG/CR-6891 |
Crack Growth Rates of Irradiated Austenitic Stainless Steel Weld Heat
Affected Zone in BWR Environments |
Jan 2006 |
ML060870193 |
| NUREG/CR-6892 |
Irradiation-Assisted Stress Corrosion Cracking Behavior of Austenitic
Stainless Steels Applicable to LWR Core Internals |
Jan 2006 |
ML060870182 |
| NUREG/CR-6888 |
Emerging Technologies in Instrumentation and Controls: An Update |
Jan 2006 |
ML060870216 |
| NUREG/CR-6895 |
Technical Review of On-Line Monitoring Techniques for Performance
Assessment: State-of-the-Art |
Jan 2006 |
ML060610394 |
| NUREG/CR-6897 |
Assessment of Void Swelling in Austenitic Stainless Steel Core Internals |
Jan 2006 |
ML060720151 |
| NUREG-1824 V1 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Main Report (Draft for Comment) |
Jan 2006 |
ML060340323 |
| NUREG-1824 V2 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire Dynamic Tools (FDTs) (Draft for Comment) |
Jan 2006 |
ML060340180 |
| NUREG-1824 V3 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire-Induced Vulnerability (FIVE-Revi) (Draft for Comment) |
Jan 2006 |
ML060340309 |
| NUREG-1824 V4 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Consolidated Fire Growth and Smoke Transport Model (CFAST) (Draft for Comment) |
Jan 2006 |
ML060340313 |
| NUREG-1824 V5 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: MAGIC (Draft for Comment) |
Jan 2006 |
ML060340315 |
| NUREG-1824 V6 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Fire Dynamics Simulator (FDS) (Draft for Comment) |
Jan 2006 |
ML060340318 |
| NUREG-1824 V7 DFC |
Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications: Experimental Uncertainty (Draft for Comment) |
Jan 2006 |
ML060340320 |
| NUREG-0800 Sec 17.5 DFC |
Standard Review Plan: Quality Assurance Program Description - Design
Certification, Early Site Permit and New License Applicants |
Jan 2006 |
ML060180622 |
| NUREG-1437 S26 DFC |
Generic Environmental Impact Statement for the License Renewal of Nuclear
Plants: Regarding Monticello Nuclear Generating Plant (Draft for Comment) |
Jan 2006 |
ML060190072 |
| NUREG-0800 Sec 6.2.1.3
R2 |
Standard Review Plan: Mass and Energy Release Analysis for Postulated
Loss-of-Coolant Accidents |
Jan 2006 |
ML060150002 |
| NUREG/CR-6866 |
Technical Bases for Regulatory Guidance on Lightning Protection in Nuclear
Power Plants |
Jan 2006 |
ML060410257 |
| NUREG-0800 Sec 2.3.1 R3 DFC |
Standard Review Plan: Regional Climatology (Draft for Comment) |
Jan 2006 |
ML053570372 |
| NUREG-0800 Sec 3.5.4.1 R3 DFC |
Standard Review Plan: Missiles Generated by Tornadoes and Extreme Winds
(Draft for Comment) |
Jan 2006 |
ML053570376 |
| NURRG-0800 Sec 15.0.2 |
Review of Transient and Accident Analysis Methods |
Dec 2005 |
ML053550265 |
| NUREG-1793 S1 |
FSER Related to Certification of the AP1000 Standard Plant Design |
Dec 2005 |
ML060330557 |
| NUREG/CR-6889 |
Seismic Analysis if Simplified Piping Systems for the NUPEC Ultimate
Strength Piping Test Program |
Dec 2005 |
ML060190048 |
| NUREG/BR-0117 #05-04 |
NMSS Licensee Newsletter |
Dec 2005 |
ML060190050 |
| NUREG-0800 Sec 6.5.2 R3 |
Standard Review Plan: Containment Spray as a Fission Product Cleanup
System |
Dec 2005 |
ML060150002 |
| NUREG-0800 Sec 12.5
R3 DFC |
Standard Review Plan: Operational Radiation Protection Program (Draft for
Comment) |
Dec 2005 |
ML060170759 |
| NUREG/CR-6572 R1 |
Kalinin VVER-1000 Nuclear Power Station Unit 1 PRA Procedures Guide for
a Probabilistic Risk Assessment (English Version) |
Dec 2005 |
ML060170179 |
| NUREG-0713 V26 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and
Other Facilities 2004 - 37th Annual Report |
Dec 2005 |
ML060110066 |
| NUREG/CR-6890 V1 |
Reevaluation of Station Blackout Risk at Nuclear Power Plants - Analysis of
Loss of Offsite Power Events: 1986-2004 |
Dec 2005 |
ML060200477 |
| NUREG/CR-6890 V2 |
Reevaluation of Station Blackout Risk at Nuclear Power Plants - Analysis of
Station Blackout Risk |
Dec 2005 |
ML060200479 |
| NUREG/CR-6890 V3 |
Reevaluation of Station Blackout Risk at Nuclear Power Plants - Resolution of
Comments |
Dec 2005 |
ML060200510 |
| NUREG-0800 13.2.1 R2 |
Standard Review Plan: Reactor Operator Training |
Dec 2005 |
ML060030205 |
| NUREG-0800 13.2.2 R2 |
Standard Review Plan: Training for Nonlicensed Plant Staff |
Dec 2005 |
ML060030199 |
| NUREG-0800 13.5.2.1 R1 |
Standard Review Plan: Operating and Emergency Operating Procedures |
Dec 2005 |
ML060030233 |
| NUREG-1839 |
Safety Evaluation Report Related to the License Renewal of the Point Beach
Nuclear Plant, Units 1 & 2 |
Dec 2005 |
ML053420129 |
| NUREG/IA-0212 V1 |
Kalinin VVER-1000 Nuclear Power Station Unit 1 PRA Beta Project,
Executive Summary (English Version) |
Nov 2005 |
ML060030237 |
| NUREG/BR-0326 |
NRC Inspector Field Observation Best Practice |
Nov 2005 |
Ml053340468 |
| NUREG/CR-6887 |
DORT/TORT Analysis of the Hatch Unit-1 Jet Pump Riser Brace Pad
Neutron Dosimetry Measurements with Comparisons to Predictions Made
with RAMA |
Nov 2005 |
ML053340460 |
| NUREG-1542 V11 |
USNRC FY 2005 Performance and Accountability Report |
Nov 2005 |
ML053200307 |
NUREG-1556 V9 R1
Errata |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Medical Use Licenses |
Nov 2005 |
ML053220013 |
| NUREG/CR-6886 DFC |
Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire
Scenario (Draft Report for Comment) |
Nov 2005 |
ML053200024 |
| NUREG-1831 V1 |
Safety Evaluation Report Related to the License Renewal of the Millstone
Power Station, Units 1 & 2 (through 3-120) |
Oct 2005 |
ML053270483 |
| NUREG-1831 V2 |
Safety Evaluation Report Related to the License Renewal of the Millstone
Power Station, Units 1 & 2 (page 3-121 to end) |
Oct 2005 |
ML053290180 |
| NUREG-1837 |
Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter
88-14 |
Oct 2005 |
ML053040160 |
| NUREG-1833 |
Technical Bases for Revision to the License Renewal Guidance Documents |
Oct 2005 |
ML052110003 |
| NUREG/CR-6885 |
Screen Penetration Test Results |
Oct 2005 |
ML053000064 |
| NUREG/CP-0192 |
Proceedings of the Nuclear Fuels Sessions of the 2004 Nuclear Safety
Research Conference October 25-27, 2004 |
Oct 2005 |
ML052980524 |
| NUREG/BR-0117 #05-03 |
NMSS Licensee Newsletter |
Oct 2005 |
ML052800011 |
| NUREG/CP-0191 V1 |
Proceedings of the Conference on Vessel Penetration Inspection Crack Growth
and Repair |
Sept 2005 |
ML053620380 |
| NUREG/CP -0191 V2 P1 |
Proceedings of the Conference on Vessel Penetration Inspection Crack Growth
and Repair |
Sept 2005 |
ML053630256 |
| NUREG/CP-0191 V2 Pt2 |
Proceedings of the Conference on Vessel Penetration Inspection Crack Growth
and Repair |
Sept 2005 |
ML053630244 |
| NUREG-1609 S1 |
Standard Review Plan for Transportation Packages for MOX-Radiation
Material |
Sept 2005 |
ML053040153 |
| NUREG-1617 S1 |
Standard Review Plan for Transportation Packages for MOX Spent Nuclear
Fuel |
Sept 2005 |
ML052980039 |
| NUREG-1832 |
Analysis of Public Comments on the Revised License Renewal Guidance
Documents |
Sept 2005 |
ML052780174 |
| NUREG-1801 V1 R1 |
Generic Aging Lessons Learned (GALL) Report: Summary |
Sept 2005 |
ML052770419 |
| NUREG-1801 V2 R1 |
Generic Aging Lessons Learned (GALL) Report:: Tabulation of Results |
Sept 2005 |
ML052780376 |
| NUREG-1800 R1 |
Standard Review Plan for Review of License Renewal Applications for
Nuclear Power Plants |
Sept 2005 |
ML052770566 |
| NUREG-1757 S1 DFC |
Consolidated NMSS Decommissioning Guidance: Updates to Implement the
Licence Termination Rule Analysis |
Sept 2005 |
ML052730115 |
| NUREG/BR-0325 |
USNRC's Decommissioning Program |
Sept 2005 |
ML052720422 |
| NUREG-1437 S24 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Nine Mile Point Nuclear Power Station, Units 1, and 2
(Draft for Comment) |
Sept 2005 |
ML052720075 |
| NUREG/BR-0053 R6 |
USNRC Regulations Handbook |
Sept 2005 |
ML052720461 |
| NUREG-1835 |
Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna
ESP Site |
Sept 2005 |
ML052710305 |
| NUREG/CR-6850 V1 |
EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities:
Summary and Overview |
Sept 2005 |
ML052580075 |
| NUREG/CR-6850 V2 |
EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities:
Detailed Methodology |
Sept 2005 |
ML052580118 |
| NUREG/CR-6881 |
Soil and Groundwater Sample Characterization and Agricultural Practices for
Assessing Food Chain Pathways in Biosphere Models |
Aug 2005 |
ML053270362 |
| NUREG-1826 |
APEX-AP1000 Confirmatory Testing to Support AP1000 Design Certification
(Non-Proprietary) |
Aug 2005 |
ML052980061 |
| NUREG-1437 S25 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Brunswick Steam Electric Plant, Units 1, and 2 (Draft for
Comment) |
Aug 2005 |
ML052380154 |
| NUREG-1834 DFC |
Environmental Impact Statement for the Proposed American Centrifuge Plant
in Piketon, Ohio (Draft for Comment) |
Aug 2005 |
ML052440433 |
| NUREG-1437 S23 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Point Beach Nuclear Plant, Units 1 and 2 (Final Report) |
Aug 2005 |
ML052230490 |
| NUREG-0936 V24 N1 |
Regulatory Agenda Semiannual Report Jan - June 2005 |
Aug 2005 |
ML052440428 |
| NUREG-1350 V17 |
Information Digest 2005-2006 |
July 2005 |
ML052620233 |
| NUREG/CR-6877 |
Characterization and Head-Loss Testing of Latent Debris from Pressurized-Water -Reactor Containment Buildings |
July 2005 |
ML052430751 |
| NUREG/CR-6878 |
Effect of Material Heat Treatment on Fatigue Crack Initiation in Austenitic
Stainless Steels in LWR Environments |
July 2005 |
ML052360545 |
| NUREG/CR-6875 |
Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials |
July 2005 |
ML052360563 |
| NUREG/CR-6880 |
Argonne Model Boiler Facility, Topical Report |
July 2005 |
ML052340242 |
| NUREG-0800 Ch13 Sec 13.1.2 - 13.1.3 |
Standard Review Plan; Conduct of Organizations; Operating Organization
(Final) |
July 2005 |
ML052150284 |
| NUREG-1791 |
Guidance for Assessing Exemption Requests from the Nuclear Power Plant
Licensed Operator Staffing Requirements Specified in 10 CFR 50.54 (m)
[Final] |
July 2005 |
ML052080125 |
| NUREG-1556 V1 R1 Errata |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Portable Gauge Licenses, Appendix H |
July 2005 |
ML052130055 |
| NUREG-1556 V2 Errata |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Industrial Radiography Licenses, Appendix F |
July 2005 |
ML052130054 |
| NUREG-1437 S22 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Millstone Power Station, Units 2, and 3 (Final Report) |
July 2005 |
ML051960293 |
| NUREG-1831 |
Safety Evaluation Report Relating to the License Renewal of the Donald C.
Cook Nuclear Plant, Units 1 & 2 (Final Report) |
July 2005 |
ML052230442 |
| NUREG-1125 V26 |
A Compilation of Reports of the Advisory Committee on Reactor Safeguards:
2004 Annual |
June 2005 |
ML052360054 |
| NUREG/CR-4667 V33 |
Environmentally Assisted Cracking in Light Water Reactors, Annual Report
January - December 2002 |
June 2005 |
ML052270046 |
| NUREG-1307 R11 |
Report on Waste Burial Charges: Changes in Decommissioning Waste
Disposal Costs at Low-Level Waste Burial Facilities |
June 2005 |
ML052010403 |
| NUREG-1829 DFC |
Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the
Elicitation Process (Draft for Comment) |
June 2005 |
ML052010464 |
| NUREG-1827 |
Safety Evaluation Report for the National Enrichment Facility in Lea County,
New Mexico |
June 2005 |
ML051780290 |
| NUREG-1828 |
Safety Evaluation Report Related to the License Renewal of the Arkansas
Nuclear One, Unit 2 |
June 2005 |
ML051730233 |
| NUREG-1437 S21 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 |
June 2005 |
ML051730443 |
| NUREG-1790 V1 |
Environmental Impact Statement for the Proposed National Enrichment
Facility in Lea County, New Mexico: Main Report, Appendices A-G |
June 2005 |
ML051730238 |
| NUREG-1790 V2 |
Environmental Impact Statement for the Proposed National Enrichment
Facility in Lea County, New Mexico: Appendices H-J |
June 2005 |
ML051730292 |
| NUREG/CR-6870 DFC |
Consideration of Geochemical Issues in Groundwater Restoration at Uranium
In-Situ Leach Mining Facilities (Draft for Comment) |
June 2005 |
ML051660393 |
| NUREG/CR-6871 DFC |
Documentation and Application of the Reactive Geochemical Transport
Model RATEQ (Draft for Comment) |
June 2005 |
ML051660389 |
| NUREG/CR-6837 V1 |
The Battelle Integrity of Nuclear Piping (BINP) Program Final Report:
Summary and Implications of Results |
June 2005 |
ML051660467 |
| NUREG/CR-6837 V2 |
The Battelle Integrity of Nuclear Piping (BINP) Program Final Report:
Appendices |
June 2005 |
ML051660518 |
| NUREG/CR-6876 |
Risk-Informed Assessment of Degradation Buried Piping Systems in Nuclear
Power Plants |
June 2005 |
ML051650146 |
| NUREG/CR-6534 V4 |
FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties |
May 2005 |
ML051440720 |
| NUREG-1650 Add 2 |
Question and Answers From the Peer Review by Contracting Parties on the
United States of America Third National Report for the Convention on
Nuclear Safety: April 2005 |
May 2005 |
ML051680184 |
| NUREG/BR-0050 R4 |
ACNW FY2005- FY2006 Action Plan |
May 2005 |
ML051650065 |
| NUREG-1556 V9 R1 |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Medical Use Licenses (Final Report) |
May 2005 |
ML051590276 |
| NUREG/CR-6874
|
GSI-191: Experimental Studies of Loss-of-Coolant-Accident-Generated
Debris Accumulation and Head Loss with Emphasis on the Effects of Calcium
Silicate Insulation. |
May 2005 |
ML051540121 |
| NUREG-1825 |
Safety Evaluation Report Related to the License Renewal of the Joseph M.
Farley Nuclear Plant, Units 1 and 2 |
May 2005 |
ML051250126 |
| NUREG/CR-6873 |
Corrosion Rate Measurements and Chemical Speciation of Corrosion Products
Using Thermodynamic Modeling of Debris Components to Support GSI-191 |
April 2005 |
ML051610123 |
| NUREG/BR-0240 R3 |
Reporting Safety Concerns to the NRC |
April 2005 |
ML051400092 |
| NUREG-1823 |
U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of
Light-Water Reactor Pressure Vessel Materials |
April 2005 |
ML051390139 |
| NUREG-1762 V1 R1 |
Integrated Issue Resolution Status Report: Chapters 1-8 |
April 2005 |
ML051360159 |
| NUREG-1762 V2 R1 |
Integrated Issue Resolution Status Report: Appendices A-D |
April 2005 |
ML051360241 |
| NUREG-0090 V27 |
Report to Congress on Abnormal Occurrences FY-2004 |
April 2005 |
ML051110725 |
| NUREG-1792 |
Good Practices for Implementing Human Reliability Analysis (Final) |
April 2005 |
ML051160213 |
| NUREG-1437 S20 |
Generic for License Renewal of Nuclear Plants: Regarding Donald C. Cook
Nuclear Plant, Units 1 and 2 (Final) |
April 2005 |
ML051150556 |
| NUREG-1817 DFC |
Environmental Impact Statement for an Early Site Permit (ESP) at the Grand
Gulf ESP Site (Draft for Comment) |
April 2005 |
ML051110531 |
| NUREG-1437 S19 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Arkansas Nuclear One, Unit 2 (Final) |
April 2005 |
ML051080538 |
| NUREG/CR-4461 R1 |
Tornado Climatology of the Contiguous United States |
April 2005 |
ML051080477 |
| NUREG-0910 R4 |
NRC Comprehensive Records Disposition Schedule |
March 2005 |
ML051390495 |
| NUREG-1821 |
Final Safety Evaluation Report on the Construction Authorization Request for
the Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South
Carolina |
March 2005 |
ML050960447 |
| NUREG/IA-0211 |
Experimental Study of Embrittlement of ZR-1%Nb Cladding Under LOCA-Relevant Conditions |
March 2005 |
ML051020065 |
| NUREG/CR-6868 |
Small-Scale Experiments: Effects of Chemical Reactions on Debris-Bed Head
Loss, A Subtask of GSI-191 |
March 2005 |
ML050900260 |
| NUREG/CR-6869 |
A Reliability Physics Model for Aging of Cable Insulation Materials |
March 2005 |
ML050940065 |
| NUREG-1350 V16 R1 |
USNRC Information Digest 2004-2005 Edition |
Feb 2005 |
ML051110550 |
| NUREG-1710 V1 |
History of Water Development at the Nevada Test Site: A Literature Review |
Feb 2005 |
ML051110144 |
| NUREG-1710 V2 |
History of Water Development in the Amargosa Desert Area: A Literature
Review |
Feb 2005 |
ML051110125 |
| NUREG-6865 |
Parametric Evaluation of Seismic Behavior of Freestanding Spent Fuel Dry
Cask Storage System |
Feb 2005 |
ML051120008 |
| NUREG-1816 |
Independent Verification of the Mitigating Systems Performance Index
(MSPI) Results For The Pilot Plants |
Feb 2005 |
ML050810636 |
| NUREG-1437 S18 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Joseph M. Farley Nuclear Plant, Units 1 and 2 (Final) |
Feb 2005 |
ML050680297 |
| NUREG-1815 DFC |
Environmental Impact Statement for an Early Site Permit (ESP) at the Exelon
ESP Site (Draft for Comment) |
Feb 2005 |
ML050610364 |
| NUREG-6866 DFC |
Technical Basis for Regulatory Guidance on Lightning Protection in Nuclear
Power Plants (Draft for Comment) |
Feb 2005 |
ML050550396 |
| NUREG/CP-0189 |
Proceedings of the USNRC/EPRI/ANL Heated Crevice Seminar |
Feb 2005 |
ML050600118 |
| NUREG-0383 V2 R25 |
Directory of Certificates of Compliance for Radioactive Materials Packages:
Certificates of Compliance |
Feb 2005 |
ML050630132 |
| NUREG-0383 V3 R22 |
Directory of Certificates of Compliance for Radioactive Materials Packages:
Report of NRC-Approved Quality Assurance Programs for Radioactive
Materials Packages |
Feb 2005 |
ML050490092 |
| NUREG-1100 V21 |
Performance Budget Fiscal Year 2006 |
Feb 2005 |
ML050480270 |
| NUREG-0936 V23 N2 |
NRC Regulatory Agenda Semiannual Report: July - December 2004 |
Jan 2005 |
ML050690266 |
| NUREG-0386 Digest 13 |
United States Nuclear Regulatory Commission Staff and Practice Digest July
1972- Jan 2004 |
Jan 2005 |
ML050550499 |
| NUREG-1482 R1 |
Guidelines for Inservice Testing at Nuclear Power Plants |
Jan 2005 |
ML050550290 |
| NUREG-1814 |
Status of Decommissioning Program: 2004 Annual Report Final Report |
Jan 2005 |
ML050480398 |
| NUREG/CR-6863 |
Development of Evacuation Time Estimate Studies for Nuclear Power Plants |
Jan 2005 |
ML050250240 |
| NUREG/CR-6864 V1 |
Identification and Analysis of Factors Affecting Emergency Evacuations:
Main Report |
Jan 2005 |
ML050250245 |
| NUREG/CR-6864 V2 |
Identification and Analysis of Factors Affecting Emergency Evacuations:
Appendices |
Jan 2005 |
ML050250219 |
| NUREG-1762 V1 |
Environmental Impact Statement for Construction and Operation of a
Proposed Mixed Oxide Fuel Fabrication at the Savannah River Site, South
Carolina: Main Report and Appendices A-E (Final Report) |
Jan 2005 |
ML050240233 |
| NUREG-1762 V2 |
Environmental Impact Statement for Construction and Operation of a
Proposed Mixed Oxide Fuel Fabrication at the Savannah River Site, South
Carolina: Appendices F-L (Final Report) |
Jan 2005 |
ML050240250 |
| NUREG-1437 V23 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Point Beach Nuclear Plant Units 1 and 2 (Draft for
Comment) |
Jan 2005 |
ML050130187 |
| NUREG-1805 |
Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for
the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program
(Final Report) |
Dec 2004 |
ML043290075 |
| NUREG/BR-0318 |
Effective Risk Communication: Guidelines for Internal Risk Communication |
Dec 2004 |
ML050960339 |
| NUREG/BR-0202 R3 |
Guidelines for Interviews With the Media |
Dec 2004 |
ML050270289 |
| NUREG/CP-0190 |
Proceedings of the ACNW Working Group on the Performance Confirmation
Plans for the Proposed Yucca Mountain High-Level Waste Repository |
Dec 2004 |
ML043580417 |
| NUREG/CR-6861 |
Barrier Integrity Research Program |
Dec 2004 |
ML043580207 |
| NUREG-1713 |
Standard Review Plan for Decommissioning Cost Estimates for Nuclear
Power Reactors |
Dec 2004 |
ML043510113 |
| NUREG-1437 S22 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Millstone Power Station, Units 2 and 3 (Draft for
Comment) |
Dec 2004 |
ML043360092 |
| NUREG/BR-0286 R1 |
ACRS 2005-08 Action Plan |
Nov 2004 |
ML050060265 |
| NUREG-1811 DFC |
Environmental Impact Statement for an Early Site Permit (ESP) at the North
Anna ESP Site (Draft for Comment) |
Nov 2004 |
ML043380308 |
| NUREG/CR-6860 |
An Assessment of Visual Testing |
Nov 2004 |
ML043630040 |
| NUREG-1437 S21 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Draft for
Comment) |
Nov 2004 |
ML043380217 |
| NUREG-1703 |
Characterization of Radioactive Slags |
Oct 2004 |
ML060470133 |
| NUREG/CP-0187 |
Proceedings of the International Workshop on Uncertainty, Sensitivity, and
Parameter Estimation for Multimedia Environmental Modeling |
Oct 2004 |
ML043440445 |
| NUREG/CR-6853 |
Comparison of Average Transport and Dispersion Among a Gaussian, a
Two-Dimensional, and a Three-Dimensional Model |
Oct 2004 |
ML043240034 |
| NUREG-1423 V14 |
A Compilation of Reports of the Advisory Committee on Nuclear Waste - July
2003 - August 2004 |
Oct 2004 |
ML043240027 |
| NUREG-0713 V25 |
Occupational Radiation Exposures at Commercial Nuclear Power Reactors
and Other Facilities 2003 |
Oct 2004 |
ML043150028 |
| NUREG-1796 |
Safety Evaluation Report Related to Dresden Nuclear Power Station, Units 2
and 3 and Quad Cities Nuclear Power Station, Units 1 and 2 |
Oct 2004 |
ML043060581 |
| NUREG-1640 V2 |
Radiological Assessments for Clearance of Materials from Nuclear Facilities:
Appendices A through E |
Oct 2004 |
ML043090271 |
| NUREG/CR-6595 R1 |
An Approach for Estimating the Frequencies of Various Containment Failure
Modes and Bypass Events |
Oct 2004 |
ML043240040 |
| NUREG/CR-6850 V1
DFC |
EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities:
Summary and Overview |
Oct 2004 |
ML042800183 |
| NUREG/CR-6850 V2
DFC |
EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities:
Detailed Methodology |
Oct 2004 |
ML042800196 |
| NUREG/CP-0188 |
Transactions of the 2004 Nuclear Safety Research Conference |
Oct 2004 |
ML042920325 |
| NUREG-1576 S1 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual
(MARLAP):l Accompaniment to CD- Executive Summary (Roadmap) |
Oct 2004 |
ML042890321 |
| NUREG/CR-6851 |
Hydrogen Effects on Air Oxidation of Zirlo Alloy |
Oct 2004 |
ML042870061 |
| NUREG/BR-0238 R12 |
Materials Annual Fee Billing Handbook |
Oct 2004 |
ML042640085 |
| NUREG-1794 |
Loss of Control of Cesium-137 Well Logging Source Resulting in Radiation
Exposures to Members of the Public |
Oct 2004 |
ML042940248 |
| NUREG-1793 V1 |
Final Safety Evaluation Report Related to Certification of the AP1000
Standard Design: Chapters 1-9 |
Sept 2004 |
ML043450333 |
| NUREG-1793 V2 |
Final Safety Evaluation Report Related to Certification of the AP1000
Standard Design: Chapters 10-20 |
Sept 2004 |
ML043450288 |
| NUREG-1793 V3 |
Final Safety Evaluation Report Related to Certification of the AP1000
Standard Design: Chapters 21-24 and Appendices |
Sept 2004 |
ML043450274 |
| NUREG/BR-0058 R4 |
Regulatory Analysis Guidelines of the USNRC |
Sept 2004 |
ML042820192 |
| NUREG/BR-0313 |
The Nuclear Regulatory Commission's Early ADR Program |
Sept 2004 |
ML042940240 |
| NUREG/BR-0314 |
Protecting Our Nation Since 9-11-01 |
Sept 2004 |
ML042650352 |
| NUREG-1640 R1 |
The United States of America Third National Report for the Convention on
Nuclear Safety |
Sept 2004 |
ML042680236 |
| NUREG-1437 S20 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Donald C. Cook Nuclear Plant, Units 1 and 2 (Draft for
Comment) |
Sept 2004 |
ML042570376 |
| NUREG-0933 S28 |
A Prioritization of Generic Safety Issues |
Aug 2004 |
ML042540049 |
| NUREG/BR-0249 R2 |
The Atomic Safety Licensing Board Panel |
Aug 2004 |
ML042460215 |
| NUREG/CR-6845 |
Sensitivity Analysis Applied to the Validation of the 10B Capture Reaction in
Nuclear Fuel Casks |
Aug 2004 |
ML042530008 |
| NUREG-0936 V23 N1 |
NRC Regulatory Agenda Semiannual Report Jan-June 2004 |
Aug 2004 |
ML042380516 |
| NUREG/CR-6849 |
Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for
AP1000 |
Aug 2004 |
ML042460184 |
| NUREG/BR-0249 R2 |
The Atomic Safety and Licensing Board Panel |
Aug 2004 |
ML042460215 |
| NUREG-1790 DFC |
Environmental Impact Statement for the Proposed National Enrichment
Facility in Lea County, New Mexico |
Aug 2004 |
ML042510184 |
| NUREG-0800 Ch13 |
Standard Review Plan; Sections 13.1.2 - 13.1.3: Operating Organization
(Draft for Comment) |
Aug 2004 |
ML041550746 |
| NUREG-1614 V3 |
USNRC Strategic Plan FY 2004-2009 |
Aug 2004 |
ML042230185 |
| NUREG-1350 V16 |
USNRC Information Digest 2004-2005 Edition |
Aug 2004 |
ML042360006 |
| NUREG-1021 R9 |
Operator Licensing Examination Standards for Power Reactors |
July 2004 |
ML051450329 |
| NUREG-1021 R9 Errata |
Operator Licensing Examination Standards for Power Reactors |
May 2005 |
ML042320438 |
| NUREG-1576 V1 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual
(MARLAP): Chapters 1-9 and Appendix A-E |
July 2004 |
ML042310547 |
| NUREG-1576 V2 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual
(MARLAP): Chapters 10-17 and Appendix F |
July 2004 |
ML042310738 |
| NUREG-1576 V3 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual
(MARLAP): Chapters 18-20 and Appendix G |
July 2004 |
ML042320083 |
| NUREG/CR-6844 V1 |
TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables
(PIRTs) for Fission Product Transport Due to Manufacturing, Operations, and
Accidents: Main Report |
July 2004 |
ML042300668 |
| NUREG/CR-6844 V2 |
TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables
(PIRTs) for Fission Product Transport Due to Manufacturing, Operations, and
Accidents: Appendices A through D |
July 2004 |
ML042300658 |
| NUREG/CR-6844 V3 |
TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables
(PIRTs) for Fission Product Transport Due to Manufacturing, Operations, and
Accidents: Appendices E through H |
July 2004 |
ML042300649 |
| NUREG-1791 DFC |
Guidance for Assessing Exemption Requests from the Nuclear Power Plant
Licensed Operator Staffing Requirements Specified in 10 CFR 50.54 (m)
(Draft for Comment) |
July 2004 |
ML041550723 |
| NUREG-1792 DFC |
Good Practices for Implementing Human Reliability Analysis (Draft for
Comment) |
July 2004 |
ML041980358 |
| NUREG-1437 S18 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Joseph M. Farley Nuclear Plant, Units 1 and 2 (Draft for
Comment) |
July 2004 |
ML024180117 |
| NUREG/CR-6848 |
Preliminary Validation of a Methodology for Assessing Software Quality |
July 2004 |
ML024150288 |
| NUREG/CP-0185 |
Proceedings of the 2003 Nuclear Safety Research Conference |
July 2004 |
ML042050210 |
| NUREG/BR-0298 R2 |
Nuclear Power Plant Licensing Process |
July 2004 |
ML042120007 |
| NUREG/CP-0152 V5 |
Proceedings of the Eighth NRC/ASME Symposium on Valve and Pump
Testing |
July 2004 |
ML041900037 |
| NUREG/CR-6846 |
Air Oxidation for Zr-Based Alloys |
July 2004 |
ML041900069 |
| NUREG-1437 S16 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Quad Cities Nuclear Power Station, Units 1 and 2 (Final) |
June 2004 |
ML041880213 |
| NUREG-1437 S17 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Dresden Nuclear Power Station, Units 2 and 3 (Final) |
June 2004 |
ML041890266 |
| NUREG-1430 V1 R3 |
Standard Technical Specifications: Babcock and Wilcox Plants -
Specifications |
June 2004 |
ML041800598 |
| NUREG-1430 V2 R3 |
Standard Technical Specifications: Babcock and Wilcox Plants - Bases |
June 2004 |
ML041830589 |
| NUREG-1431 V1 R3 |
Standard Technical Specifications: Westinghouse Plants - Specifications |
June 2004 |
ML041830612 |
| NUREG-1431 V2 R3 |
Standard Technical Specifications: Westinghouse Plants - Bases |
June 2004 |
ML041830205 |
| NUREG-1432 V1 R3 |
Standard Technical Specifications: Combustion Engineering Plants -
Specifications |
June 2004 |
ML041830597 |
| NUREG-1432 V2 R3 |
Standard Technical Specifications: Combustion Engineering Plants - Bases |
June 2004 |
ML041830097 |
| NUREG-1433 V1 R3 |
Standard Technical Specifications: General Electric BWR/4 Plants -
Specifications |
June 2004 |
ML041910194 |
| NUREG-1433 V2 R3 |
Standard Technical Specifications: General Electric BWR/4 Plants - Bases |
June 2004 |
ML041910220 |
| NUREG-1434 V1 R3 |
Standard Technical Specifications: General Electric BWR/6 Plants -
Specifications |
June 2004 |
ML041910204 |
| NUREG-1434 V2 R3 |
Standard Technical Specifications: General Electric BWR/6 Plants - Bases |
June 2004 |
ML041910220 |
| NUREG/BR-0301 R1 |
Licensing Support Network for Documents Relating to the Yucca Mountain
Licensing Proceeding |
June 2004 |
ML041760035 |
| NUREG-1640 V4 |
Radiological Assessments for Clearance of Materials from Nuclear Facilities:
Appendices H through O |
May 2004 |
ML041550973 |
| NUREG-1125 V25 |
A Compilation of Reports of the Advisory Committee on Reactor Safeguards:
2003 Annual |
May 2004 |
ML041590539 |
| NUREG-1788 |
CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a
PWR Severe Accident |
May 2004 |
ML041380224 |
| NUREG-1786 |
Safety Evaluation Report Related to the License Renewal of R.E. Ginna
Nuclear Power Plant |
May 2004 |
ML041400502 |
| NUREG-1707 V6 |
Interagency Steering Committee on Radiation Standards (ISCORS): 2003
Annual Report |
May 2004 |
ML041390293 |
| NUREG/BR-0310 |
Office of Nuclear Security and Incident Response: Career Opportunities |
May 2004 |
ML041270050 |
| NUREG/CR-6842 |
Advanced Reactor Licensing: Experience with Digital I&C Technology in
Evolutionary Plants |
April 2004 |
ML041910046 |
| NUREG/BR-0099 R11 |
USNRC Protecting Public Health and Safety |
April 2004 |
ML041130019 |
| NUREG-1556 V3 R1 |
Consolidated Guidance About Materials Licenses: Applications for Sealed
Source and Device Evaluation and Registration (Final Report) |
April 2004 |
ML041340618 |
| NUREG-1789 |
10 CFR Part 52 Construction Inspection Program Framework Document |
April 2004 |
ML041340633 |
| NUREG-0090 V26 |
Report to Congress on Abnormal Occurrences: Fiscal Year 2003 |
April 2004 |
ML041270308 |
| NUREG/CR-6841 |
A Risk-Informed Basis for Establishing Non-Fixed Surface Contamination
Limits for Spent Fuel Transportation Casks |
April 2004 |
ML041140485 |
| NUREG/CR-6843 |
Combined Estimation of Hydrogeologic Conceptual Model and Parameter
Uncertainty |
March 2004 |
ML041260323 |
| NUREG/BR-0168 R3 |
Guide for Information Technology Security: Policy for Processing
Unclassified Safeguards Information (SGI) on NRC Computers |
March 2004 |
ML041130006 |
| NUREG-1787 |
Safety Evaluation Report Related to the License Renewal of Virgil C. Summer
Nuclear Station, Unit 1 |
March 2004 |
ML041040070 |
| NUREG-1635 V6 |
Review and Evaluation of the Nuclear Regulatory Commission Safety
Research Program: A Report to the U.S. Nuclear Regulatory Commission |
March 2004 |
ML040990584 |
| NUREG-1785 |
Safety Evaluation Report Related to the License Renewal of H.B. Robinson
Steam Electric Plant, Unit 2 |
March 2004 |
ML040990702 |
| NUREG/CP-0184 |
Advisory Committee Nuclear Waste NRC/DOE Performance Assessments
Workshop |
March 2004 |
ML040990484 |
| NUREG/BR-0309 |
Serving on the Advisory Committee on the Medical Uses of Isotopes
(ACMUI) - A Member's Guide |
March 2004 |
ML040790351 |
| NUREG/CR-6817 |
A Generalized Procedure for Generating Flaw-Related Inputs for the FAVOR
Code |
March 2004 |
ML040830499 |
| NUREG/BR-0298 R1 |
Nuclear Power Plant Licensing Process |
March 2004 |
ML040770057 |
| NUREG/CR-6682 S1 |
Summary and Categorization of Public Comments on Controlling the
Disposition of Solid Materials |
March 2004 |
ML040720691 |
| NUREG-1100 V20 |
Performance Budget Report Fiscal Year 2005 |
Feb 2004 |
ML061140100 |
| NUREG-0711 R2 |
Human Factors Engineering Program Review Model |
Feb 2004 |
ML040770540 |
| NUREG-1764 |
Guidance for the Review of Changes to Human Actions (Final Report) |
Feb 2004 |
ML040770551 |
| NUREG-0800 Sec 19.1 |
Standard Review Plan: Section 19.1, "Determining the Technical Adequacy
of Probabilistic Risk Assessment Results for Risk-Informed Activities" |
Feb 2004 |
ML040920144 |
| NUREG-0800 Sec 18.0
R1 |
Standard Review Plan: Section 18.0, "Human Factors Engineering" |
Feb 2004 |
ML040920139 |
| NUREG/BR-0308 |
Effective Risk Communication: The NRC's Guideline for External Risk
Communication |
Feb 2004 |
ML040690412 |
| NUREG/BR-0308 S1 |
Effective Risk Communication: The NRC's Guideline for External Risk
Communication (Quick Reference Guide) |
Feb 2004 |
ML040690441 |
| NUREG/CR-6838 |
Technical Basis for Regulatory Guidance for Assessing Exemptions Requests
from Nuclear Power Plant Licensed Operator Staffing Requirements Specified
in 10CFR.54(m) |
Feb 2004 |
ML040580289 |
| NUREG-1437 S15 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Virgil C. Summer Nuclear Power Station (Final Report) |
Feb 2004 |
ML040540526 |
| NUREG-1542 V9 |
USNRC Performance and Accountability Report - FY2003 |
Jan 2004 |
ML040420132 |
| NUREG-1773 |
Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at
the Idaho National Engineering and Environmental Laboratory in Butte
County, Idaho (Final Report) |
Jan 2004 |
ML040490135 |
| NUREG/CR-6840 |
The Technical Basis for the NRC's Guidelines for External Risk
Communication |
Jan 2004 |
ML040540526 |
| NUREG-0936 V22 N2 |
USNRC Regulatory Agenda Semiannual Report Jul - Dec 2003 |
Jan 2004 |
ML040440395 |
| NUREG/CR-6839 |
Fort Saint Vrain Gas Cooled Reactor Operational Experience |
Jan 2004 |
ML040340070 |
| NUREG-1778 DFC |
Knowledge Base for Post-Fire Safe-Shutdown Analysis (Draft for Comment) |
Jan 2004 |
ML040210151 |
| NUREG-1437 S14 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding R.E. Ginna Nuclear Power Plant (Final Report) |
Jan 2004 |
ML040230341 |
| NUREG/CR-6820 |
Application of Surface Complexation Modeling to Describe Uranium (VI)
Adsorption and Retardation at the Uranium Mill Tailings Site at Naturita,
Colorado |
Dec 2003 |
ML040210168 |
| NUREG-0933 S27 |
A Prioritization of Generic Safety Issues |
Dec 2003 |
ML040070409 |
| NUREG/CR-6577 S2 |
U.S. Nuclear Power Plant Operating Cost and Experience Summaries |
Dec 2003 |
ML040070512 |
| NUREG-1437 S13 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding H.B. Robinson Steam Electric Plant, Unit No. 2 (Final
Report) |
Dec 2003 |
ML033450517 |
| NUREG-1614 V3 |
FY 2004-2009 Strategic Plan (Draft for Comment) |
Dec 2003 |
ML033360673 |
| NUREG-1437 S17 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants, Regarding Dresden Nuclear Power Station, Units 2 and 3 (Draft for
Comment) |
Dec 2003 |
ML033280676 |
| NUREG-1784 |
Operating Experience Assessment - Effects of Grid Events on Nuclear Power
Plant Performance |
Dec 2003 |
ML033530400 |
| NUREG/CP-0183 |
Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture
Workshop |
Nov 2003 |
ML033500412 |
| NUREG-1783 DFC |
Interagency Steering Committee on Radiation Standards (ISCORS)
Assessment of Radioactivity in Sewage Sludge: Modeling to Assess
Radiation Doses (Draft for Comment) |
Nov 2003 |
ML033280626 |
| NUREG-1781 |
CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a
PWR Severe Accident |
Nov 2003 |
ML033140399 |
| NUREG-1775 |
Interagency Steering Committee on Radiation Standards (ISCORS)
Assessment of Radioactivity in Sewage Sludge: Radiological Survey Results
and Analysis |
Nov 2003 |
ML033140171 |
| NUREG-1437 S16 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Quad Cities Nuclear Power Station, Units 1 and 2 (Draft
for Comment) |
Nov 2003 |
ML033020456 |
| NUREG-0713 Vol 24 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and
Other Facilities 2002," Thirty-Fifth Annual Report |
Oct 2003 |
ML033230542 |
| NUREG-0430 V22 |
Licensed Fuel Facility Status Report - Inventory Difference Data July 1, 2001
- June 30, 2002 |
Oct 2003 |
ML033210030 |
| NUREG/CP-0181 |
International Collaborative Project to Evaluate Models for Nuclear Power
Plant Applications: Proceedings of 5th Meeting |
Oct 2003 |
ML033370128 |
| NUREG-0933 S26 |
A Prioritization of Generic Safety Issues |
Oct 2003 |
ML033100437 |
| NUREG/CR-6818 |
Drop Test Results for Combustion Engineering Model ABB-2901 Fuel Pellet
Shipping Package |
Oct 2003 |
ML033030180 |
| NUREG-1782 |
Safety Evaluation Report Related to the License Renewal of the Fort Calhoun
Station, Unit 1 |
Oct 2003 |
ML033020438 |
| NUREG-1777 |
Regulatory Effectiveness Assessment of Option B of Appendix J |
Oct 2003 |
ML033030547 |
| NUREG-1779 |
Safety Evaluation Report Related to License Renewal of St. Lucie Nuclear
Plant, Units 1 and 2 |
Sept 2003 |
ML032940205 |
| NUREG/CP-0182 |
Proceedings of the Advisory Committee on Nuclear Waste Transportation
Working Group Meeting |
Sept 2003 |
ML032880275 |
| NUREG/CR-6834 |
Circuit Analysis - Failure Mode and Likelihood Analysis |
Sept 2003 |
ML032731464 |
| NUREG/CR-6782 |
Comparison of U.S. Military and International Electromagnetic Compatibility
Guidance |
Sept 2003 |
ML033000345 |
| NUREG/CR-5609 |
Electromagnetic Compatibility Testing for Conducted Susceptibility Along
Interconnecting Signal Lines --Final Report |
Sept 2003 |
ML032960137 |
| NUREG/CR-6823 |
Handbook of Parameter Estimation for Probabilistic Risk Assessment |
Sept 2003 |
ML032900131 |
| NUREG/CR-6835 |
Effects of Fuel Failure on Criticality Safety and Radiation Dose for Spent Fuel
Casks |
Sept 2003 |
ML032880058 |
| NUREG/CR-6836 |
Comparing Ground-Water Recharge Estimates Using Advanced Monitoring
Techniques and Models |
Sept 2003 |
ML032880047 |
| NUREG-1780 |
Regulatory Effectiveness of the Anticipated Transient Without Scram Rule |
Sept 2003 |
ML032790414 |
| NUREG/CR-6834 |
Circuit Analysis - Failure Mode and Likelihood Analysis |
Sept 2003 |
ML032731464 |
| NUREG/CR-6833 |
Formal Methods of Decision Analysis Applied to Prioritization of Research
and Other Topics |
Sept 2003 |
ML033000339 |
| NUREG-1423 V13 |
A Compilation of Reports of the Advisory Committee on Nuclear Waste: July
2002 - June 2003 |
Sept 2003 |
ML032681058 |
| NUREG/CR-6804 |
Second U.S. Nuclear Regulatory Commission International Steam Generator
Tube Integrity Research Program |
Sept 2003 |
ML032681071 |
| NUREG/CR-6831 |
Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage |
Sept 2003 |
ML032731021 |
| NUREG/CR-6815 |
Review of the Margins for ASME Code Fatigue Design Curve - Effects of
Surface Roughness and Material Variability |
Sept 2003 |
ML032670639 |
| NUREG-1757 V1 R1 |
Consolidated NMSS Decommissioning Guidance: Decommissioning Process
for Materials Licensees --Final Report |
Sept 2003 |
ML032530410 |
| NUREG-1757 V2 |
Consolidated NMSS Decommissioning Guidance: Characterization, Survey,
and Determination |
