| Documents added January 1, 2000 through August 7, 2008 |
| 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/BR-0277 R2 |
Making Our Business Your Business |
July 2008 |
ML082200111 |
| NUREG/CR-6967 |
Cladding Embrittlement During Postulated Loss-of-Coolant Accidents |
July 2008 |
ML082130389 |
| NUREG-1910 V1 DFC |
Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facility: Chapters 1-4 (Report for Comment) |
July 2008 |
ML082030184 |
| NUREG-1910 V2 DFC |
Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facility: Chapters 5-12, Appendices A-F (Report for Comment) |
July 2008 |
ML082000997 |
NUREG-1910 V2
Errata DFC |
Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facility: Appendices C, D, and F (Report for Comment) |
July 2008 |
ML082100044 |
| NUREG/BR-0006 R7 |
Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M), Effective Date: January 1, 2009." |
June 2008 |
ML082100190 |
| NUREG-1885 R1 |
Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category I Fuel Cycle Facilities: Results and Status Update |
June 2008 |
ML081920329 |
| NUREG/CP-0152 V7 |
Proceedings of the Ninth NRC/ASME Symposium on Valves, Pumps and Inservice Testing – July 14-16, 2006 |
June 2008 |
ML081900137 |
| NUREG/BR-0117 #08-01 |
FSME Licensee Newsletter |
June 2008 |
ML081580277 |
| NUREG/CR-6964 |
Crack Growth Rates and Metallographic Examination of Alloy
600 and Alloy 82/182 from Field
Components and Laboratory Material Tested in PWR Environments |
May 2008 |
ML081690334 |
| NUREG/BR-0352 |
FCIX 2008: Fuel Cycle Information Exchange |
May 2008 |
ML081580275 |
| NUREG-1907 V1 |
Safety Evaluation Report Relating to the License Renewal
of Vermont Yankee Nuclear Power Station |
May 2008 |
ML081430057 |
| NUREG-1907 V2 |
Safety Evaluation Report Relating to the License Renewal
of Vermont Yankee Nuclear Power Station |
May 2008 |
ML081430109 |
NUREG/CR-6895 V2 |
Technical Review of On-Line
Monitoring Techniques for Performance Assessment: Theoretical Issues |
May 2008 |
ML081430058 |
| NUREG-1886 DFC |
Joint Canada-United States Guide for Approval of Type B(U)
and Fissile Material Transportation Packages |
May 2008 |
ML073300230 |
| NUREG-1888 |
Environmental Impact Statement for the Reclamation of the
Sequoyah Fuels Corporation Site in Gore, Oklahoma (Final Report) |
May 2008 |
ML081300103 |
| 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-1905 |
Safety Evaluation Report Relating to the License Renewal
of James A. FitzPatrick Nuclear Power Plant |
April 2008 |
ML081510826 |
| NUREG-0090 V30 |
Report to Congress on Abnormal Occurrences – Fiscal Year
2007 |
April 2008 |
ML081300424 |
| NUREG-1908 V1 |
Information Technology / Information Management Strategic
Plan |
April 2008 |
ML081270246 |
| 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-1635 V8 |
Review and Evaluation of the
Nuclear Regulatory Commission Safety Research Program: A Report to the U.S.
Nuclear Regulatory Commission |
March 2008 |
ML081430059 |
| 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 of Radiological Criteria-- Final Report |
Sept 2003 |
ML032530405 |
| NUREG-1757 V3 |
Consolidated NMSS Decommissioning Guidance: Financial Assurance,
Recordkeeping, and Timeliness--Final Report |
Sept 2003 |
ML032471471 |
| NUREG-1777 |
Regulatory Effectiveness Assessment of Option B of Appendix J |
Aug 2003 |
ML032510030 |
| NUREG/BR-0010, R4 |
Citizen's Guide to U.S. Nuclear Regulatory Commission Information |
Aug 2003 |
ML032660837 |
| NUREG-0936 V22 N1 |
NRC Regulatory Agenda, Semiannual Report, January - June 2003 |
Aug 2003 |
ML032540376 |
| NUREG-1748 |
Environmental Review Guidance for Licensing Actions Associated with
NMSS Programs, Final Report. |
Aug 2003 |
ML032540811 |
| NUREG/CR-6832 |
Regulatory Effectiveness of Unresolved Safety Issue (USI) A-45, "Shutdown
Decay Heat Removal Requirements" |
Aug 2003 |
ML032550456 |
| NUREG/CR-6825 |
Literature Review and Assessment of Plant and Animal Transfer Factors Used
in Performance Assessment Modeling |
Aug 2003 |
ML032680646 |
| NUREG-1437 S12 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Fort Calhoun Station, Unit 1, Final Report |
Aug 2003 |
ML032230075 |
| NUREG/BR-0006 R6 |
Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC
Forms 741 and 740M) Effective Date: October 1, 2003 |
Aug 2003 |
ML032540406 |
NUREG/BR-0006 R6
Errata |
Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC
Forms 741 and 740M) Effective Date: October 1, 2003 |
Dec 2005 |
ML060300140 |
| NUREG/BR-0007 R5 |
Instructions for the Preparation and Distribution of Material Status Reports
(DOE/NRC Forms 742 and 742C) Effective Date: October 1, 2003 |
Aug 2003 |
ML032540392 |
NUREG/BR-0007 R5
Errata |
Instructions for the Preparation and Distribution of Material Status Reports
(DOE/NRC Forms 742 and 742C) Effective Date: October 1, 2003 |
Jan 2006 |
ML060300141 |
| NUREG/CR-6826 |
Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless
Steels |
Aug 2003 |
ML032320557 |
| NUREG/BR-0146 R3 |
The IG at the NRC |
Aug 2003 |
ML032410486 |
| NUREG-1776 |
Regulatory Effectiveness of the Station Blackout Rule |
Aug 2003 |
ML032450542 |
| NUREG/CR-6595 R1
DFC |
An Approach for Estimating the Frequencies of Various Containment Failure
Modes and Bypass Events (Draft For Comment) |
Aug 2003 |
ML032330225 |
| NUREG/CR-6525 R1 |
SECPOP 2000: Sector Population, Land Fraction, and Economic Estimation
Program |
Aug 2003 |
ML032310279 |
| NUREG/CR-6824 |
Materials Behavior in HTGR Environments |
July 2003 |
ML032370015 |
| NUREG/CR-6814 |
Final Report on Advanced Nondestructive Evaluation for Steam Generator
Tubing for the Second International Steam Generator Tube Integrity Program |
July 2003 |
ML032471423 |
| NUREG-1774 |
A Survey of Crane Operating Experience at U.S. Nuclear Power Plants From
1968 Through 2002 |
July 2003 |
ML032060160 |
| NUREG/BR-0240 R 2 |
Reporting Safety Concerns to NRC |
July 2003 |
ML032390327 |
| NUREG/CR-6805 |
A Comprehensive Strategy of Hydrogeologic Modeling and Uncertainty
Analysis for Nuclear Facilities and Sites |
July 2003 |
ML032470827 |
| NUREG-1415 V15 N2 |
Office of the Inspector General Semiannual Report |
July 2003 |
ML031920600 |
| NUREG-1804 R2 |
Yucca Mountain Review Plan: Final Report |
July 2003 |
ML032030389 |
| NUREG-1620 R1 |
Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings
Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of
1978 |
June 2003 |
ML032250190 |
| NUREG-1569 |
Standard Review Plan for In Situ Leach Uranium Extraction License
Applications |
June 2003 |
ML032250177 |
| NUREG-1640 V1 |
Radiological Assessments for Clearance of Materials From Nuclear Facilities:
Main Report |
June 2003 |
ML032250178 |
| NUREG-1640 V3 |
Radiological Assessments for Clearance of Materials From Nuclear Facilities:
Appendices F and G |
June 2003 |
ML032250706 |
| NUREG-0386 Digest N12 |
United States Nuclear Regulatory Commission Staff Practice and Procedure
Digest Commission, Appeal Board and Licensing Board Decisions July 1972 -
June 30, 2002. |
June 2003 |
ML032060515 |
| NUREG-1805 V1 DFC |
Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for
the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program
(Draft or Comment) |
June 2003 |
ML031990145 |
| NUREG-1805 V2 DFC |
Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for
the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program:
Appendices (Draft for Comment) |
June 2003 |
ML031980360 |
| NUREG/CR-6811 |
Strategies for Application of Isotopic Uncertainties in Burnup Credit |
June 2003 |
ML032130638 |
| NUREG-1125 V24 |
A Compilation of Reports of The Advisory Committee on Reactor Safeguards,
2002 Annual |
June 2003 |
ML032020395 |
| NUREG-1635 V5 |
Review and Evaluation of the Nuclear Regulatory Commission Safety
Research Program |
June 2003 |
ML031920286 |
| NUREG-1773 |
Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at
the Idaho National Engineering and Environmental Laboratory in Butte
County, Idaho," Draft Report for Comment |
June 2003 |
ML031810193 |
| NUREG-1437 S15 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Virgil C. Summer Nuclear Station (Draft for Comment) |
June 2003 |
ML031960328 |
| NUREG/CR-6822 |
Collaborative Study of NUPEC Seismic Field Test Data for NPP Structures |
June 2003 |
ML031910007 |
| NUREG-1437 S14 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding R.E. Ginna Nuclear Power Plant (Draft for Comment) |
June 2003 |
ML031750834 |
| NUREG/CR-4667 V32 |
Environmentally Assisted Cracking in Light Water Reactors, Annual Report
January - December 2001 |
June 2003 |
ML031750770 |
| NUREG/CR-6819 V1 |
Common-Cause Failure Event Insights: Emergency Diesel Generators |
May 2003 |
ML031710318 |
| NUREG/CR-6819 V2 |
Common-Cause Failure Event Insights: Motor-Operated Valves |
May 2003 |
ML031710328 |
| NUREG/CR-6819 V3 |
Common-Cause Failure Event Insights: Pumps |
May 2003 |
ML031710336 |
| NUREG/CR-6819 V4 |
Common-Cause Failure Event Insights: Circuit Breakers |
May 2003 |
ML031710861 |
| NUREG-1707 V5 |
Interagency Steering Committee on Radiation Standards: 2002 Annual Report |
May 2003 |
ML031840320 |
| NUREG-6778 |
The Effects of Composition and Heat Treatment on Hardening and
Embrittlement of Reactor Pressure Vessel Steels |
May 2003 |
ML031700122 |
| NUREG/CR-6792 |
Behavior of PWR Reactor Coolant System Components, Other than Steam
Generator Tubes, Under Severe Accident Conditions, Phase I Final Report |
May 2003 |
ML031500699 |
| NUREG/CR-6802 |
Recommendations for Shielding Evaluations for Transport & Storage
Packages |
May 2003 |
ML031330514 |
| NUREG-1437 S11 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants, Supplement 11 Regarding St. Lucie Units 1 and 2, Final Report |
May 2003 |
ML031360709 |
| NUREG-1437 S13 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding H. B. Robinson Steam Electric Plant, Unit 2 (Draft for
Comment) |
May 2003 |
ML031250201 |
| NUREG/BR-0135 R3 |
Drug- Free Workplace Program |
April 2003 |
ML031500691 |
| N/IA-0209 |
Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR Transient
Codes and Updating of MATPRO Package for Modeling of LOCA and RIA
Validation Cases with Zr-1%Nb (VVER type) Cladding |
April 2003 |
ML031340376 |
| NUREG/BR-0007 R4 |
Instructions for Preparation & Distribution of Material Status Reports,
(DOE/NRC Forms 742 and 742C), Effective Date: October 1, 2003 |
April 2003 |
ML031120372 |
| NUREG/BR-0006 R5 |
Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC
Forms 741 and 740M), Effective Date: October 1, 2003 |
April 2003 |
ML031120440 |
| NUREG/CR-6813 |
Issues and Recommendations for Advancement of PRA Technology in
Risk-Informed Decision Making |
April 2003 |
ML031060514 |
| NUREG-1771 |
U.S. Operating Experience With Thermally Treated Alloy 600 Steam
Generator Tubes |
April 2003 |
ML031140094 |
| NUREG-1700 R1 |
Standard Review Plan for Evaluating Nuclear Power Reactor License
Termination Plans |
April 2003 |
ML031270391 |
| NUREG-0430 V21 |
Licensed Fuel Facility Status Report: Inventory Difference Data July 2000 -
June 2001 |
April 2003 |
ML031000113 |
| NUREG-0090 V25 |
Report to Congress on Abnormal Occurrences, Fiscal Year 2002 |
April 2003 |
ML031000094 |
| NUREG/CR-6809 |
Posttest Analysis of the NUPEC/NRC 1:4 Scale Prestressed Concrete
Containment Vessel Model |
March 2003 |
ML031830555 |
| NUREG/CR-6810 |
Overpressurization Test of a 1:4 Scale Prestressed Concrete Containment
Vessel Model |
March 2003 |
ML032040014 |
| NUREG/CR-6812 |
Emerging Technologies in Instrumentation and Controls |
March 2003 |
ML031900433 |
| NUREG/CP-0180 |
Proceedings of the 2002 Nuclear Safety Research Conference, Held at
Marriott Hotel at Metro Center Washington, DC, October 28-30, 2002 |
March 2003 |
ML031060154 |
| NUREG/CR-6801 |
Recommendations for Addressing Axial Burnup in PWR Burnup Credit
Analyses |
March 2003 |
ML031110292 |
| NUREG-0383 V2 R24 |
Directory of Certificates of Compliance for Radioactive Materials Packages,
Certificates of Compliance |
March 2003 |
ML031080247 |
| NUREG-0383 V3 R21 |
Directory of Certificates of Compliance for Radioactive Materials Packages.
Report of NRC-Approved Quality Assurance Programs for Radioactive
Materials Packages |
March 2003 |
ML031070443 |
| NUREG-1772 |
Safety Evaluation Report Related to the License Renewal of McGuire Nuclear
Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 & 2 |
March 2003 |
ML030850251 |
| NUREG-1769 |
Safety Evaluation Report Related to License Renewal of Peach Bottom
Atomic Power Station, Units 2 & 3 |
March 2003 |
ML031010136 |
| NUREG/CR-6799 |
Analysis of Rail Car Components Exposed to Tunnel Fire Environment |
March 2003 |
ML031050501 |
| NUREG/CR-6807 |
Results of NRC-Sponsored Stellite 6 Aging & Friction Testing |
March 2003 |
ML030850725 |
| NUREG/CR-6806 |
MOV Stem Lubricant Aging Research |
March 2003 |
ML030780590 |
| NUREG/CR-6800 |
Assessment of Reactivity Margins & Loading Curves for PWR Burnup-Credit
Cask Designs |
March 2003 |
ML031110280 |
| NUREG/CR-6808 |
Knowledge Base for the Effect of Debris on Pressurized Water Reactor
Emergency Core Cooling Sump Performance |
Feb 2003 |
ML030920542 |
| NUREG/CR-6795 |
A Comparison of Three Round Robin Studies on ISI Reliability of Wrought
Stainless Steel Piping |
Feb 2003 |
ML030710592 |
| NUREG-1767 DFC |
Environmental Impact Statement on Construction & Operation of a Mixed
Oxide Fuel Fabrication Facility at Savannah River Site, South Carolina (Draft
For Comment) |
Feb 2003 |
ML030520627 |
| NUREG/CR-6793 |
Numerical Simulation of the Howard Street Tunnel Fire, Baltimore, Maryland,
July 2001 |
Feb 2003 |
ML030550670 |
| NUREG-1768 DFC |
United States Nuclear Regulatory Commission Package Performance Study
Test Protocols (Draft For Comment) |
Feb 2003 |
ML030510389 |
| NUREG-1100 V19 |
Budget Estimates and Performance Plan Fiscal Year 2004 |
Feb 2003 |
ML030380500 |
| NUREG-1542 V8 |
USNRC Performance and Accountability Report - FY2002 |
Jan 2003 |
ML040910017 |
| NUREG-0936 V21 N2 |
NRC Regulatory Agenda Semiannual Report, July - December 2002 |
Jan 2003 |
ML030570362 |
| NUREG/CR-6798 |
Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the
Takahama-3 Reactor |
Jan 2003 |
ML030570346 |
| NUREG-1556 V9 App BB |
Consolidated Guidance About Materials Licenses, Program-Specific Guidance
About Medical Use Licenses: Appendix BB (Final Report) |
Jan 2003 |
ML030440154 |
| NUREG/CR-6781 |
Recommendations on the Credit for Cooling Time in PWR Burnup Credit
Analyses |
Jan 2003 |
ML030290585 |
| NUREG-1437 S10 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Peach Bottom Atomic Power Station, Units 2 & 3 (Final
Report) |
Jan 2003 |
ML030270059 |
| NUREG/CR-6773 |
GSI-191: Integrated Debris-Transport Tests in Water Using Simulated
Containment Floor Geometries |
Dec 2002 |
ML030160807 |
| NUREG/CR-6794 |
Evaluation of Aging and Environmental Qualification Practices for Power
Cables Used in Nuclear Power Plants |
Dec 2002 |
ML030130268 |
| NUREG/CR-6477 |
Revised Analysis of Decommissioning Reference Non-Fuel-Cycle Facilities |
Dec 2002 |
ML030160573 |
| NUREG-1766 |
Safety Evaluation Report Related to the License Renewal of North Anna
Power Station, Units 1 and 2, and Surry Power Station, Units 1 and 2 |
Dec 2002 |
ML030160853 |
| NUREG-1765 |
Basis Document for Large Early Release Frequency (LERF) Significance
Determination Process (SDP) Inspection Findings that May Affect LERF. |
Dec 2002 |
ML030240484 |
| NUREG-1437 S12 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Fort Calhoun Nuclear Station, Unit 1 (Draft for Comment) |
Dec 2002 |
ML030080489 |
| NUREG-1757 V3 DFC |
Consolidated NMSS Decommissioning Guidance: Financial Assurance,
Recordkeeping, and Timeliness (Draft for Comment) |
Dec 2002 |
ML023650398 |
| NUREG-1764 DFC |
Guidance for the Review of Changes to Human Actions (Draft for Comment) |
Dec 2002 |
ML023650586 |
NUREG-0800
Section 18.0 |
Standard Review Plan: Human Factors Engineering (Draft for Comment) |
Dec 2002 |
ML023650383 |
NUREG-0800
Section 14.2.1 |
Standard Review Plan: Generic Guidelines for Extended Power Uprate
Testing Programs (Draft for Comment) |
Dec 2002 |
ML030080406 |
NUREG-0800
Section 13.5.2.1 |
Standard Review Plan: Operating and Emergency Operating Procedures (Draft
for Comment) |
Dec 2002 |
ML023650356 |
NUREG-0800
Section 13.2.2 |
Standard Review Plan: Training for Nonlicensed Plant Staff (Draft for
Comment) |
Dec 2002 |
ML023650420 |
NUREG-0800
Section 13.2.1 |
Standard Review Plan: Reactor Operator Training (Draft for Comment) |
Dec 2002 |
ML023650427 |
| NUREG/BR-0303 |
Guidance for Performance-Based Regulation |
Dec 2002 |
ML023610315 |
| NUREG-1437 S8 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding McGuire Nuclear Station, Units 1 and 2 (Final) |
Dec 2002 |
ML030020238 |
| NUREG-1437 S9 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Catawba Nuclear Station Units 1 & 2 (Final) |
Dec 2002 |
ML030020356 |
| NUREG-0586, S1 V1 |
Generic Environmental Impact Statement on Decommissioning of Nuclear
Facilities Regarding the Decommissioning of Nuclear Power Reactors Main
Report, Appendices A through M (Final) |
Nov 2002 |
ML023470327 |
| NUREG-0586 S1 V2 |
Generic Environmental Impact Statement on Decommissioning of Nuclear
Facilities: Supplement 1 Regarding the Decommissioning of Nuclear Power
Reactors -- Appendices N, O, and P (Final) |
Nov 2002 |
ML023500228 |
| NUREG/CP-0179 |
Proceedings of the International Conference on Wire System Aging, Held at
the Double Tree Hotel, Rockville, Maryland, April 23-25, 2002 |
Nov 2002 |
ML023470266 |
| NUREG/BR-0299 |
WEB-BASED Public Access to ADAMS |
Nov 2002 |
ML023540388 |
| NUREG/CR-6791 |
Eddy Current Reliability Results From The Steam Generator Mock-up
Analysis Round Robin |
Nov 2002 |
ML023390227 |
| NUREG/CR-6789 |
Results From Pressure and Leak-Rate Testing of Laboratory-Degraded Steam
Generator Tubing |
Nov 2002 |
ML023390244 |
| NUREG-1437 S7 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding North Anna Power Station, Units 1 and 2 (Final) |
Nov 2002 |
ML023380574 |
| NUREG-1437 S6 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants, Regarding Surry Station, Units 1 and 2 (Final) |
Nov 2002 |
ML023310721 |
| NUREG-1556 V9 |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Medical Use Licenses (Final) |
Oct 2002 |
ML023120182 |
| NUREG-1556 V9 Errata |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Medical Use Licenses (Nov 2002) |
Oct 2002 |
ML030360308 |
| NUREG-1307 R10 |
Report on Waste Burial Charges, Changes in Decommissioning Waste
Disposal Costs at Low-Level Waste Burial Facilities |
Oct 2002 |
ML023180336 |
| NUREG/CR-6607 |
Guidance For Performing Probabilistic Seismic Hazard Analysis For A
Nuclear Plant Site: Example Application To The Southeastern United States |
Oct 2002 |
ML023090048 |
| NUREG-1437 S11 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants, Regarding St. Lucie Units 1 and 2 (Draft for Comment) |
Oct 2002 |
ML023020107 |
| NUREG/CR-6783 |
Structural Seismic Fragility Analysis of the Surry Containment |
Oct 2002 |
ML022900737 |
| NUREG/CP-0178 |
Transactions of the 2002 Nuclear Safety Research Conference, October
28-30, 2002 |
Oct 2002 |
ML022890422 |
| NUREG/CR-6788 |
Evaluation of Aging and Qualification Practices for Cable Splices Used in
Nuclear Plants |
Sept 2002 |
ML022890408 |
| NUREG/CR-6786 |
ANL/CANTIA: A Computer Code for Steam Generator Integrity Assessments |
Sept 2002 |
ML022810455 |
| NUREG/CR-6785 |
Evaluation of Eddy Current Reliability from Steam Generator Mock-Up
Round-Robin |
Sept 2002 |
ML022980099 |
| NUREG-0713 V23 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and
Other Facilities - 2001 |
Sept 2002 |
ML022820374 |
| NUREG/CR-6749 |
Integrating Digital and Conventional Human-System Interfaces: Lessons
Learned From A Control Room Modernization Program |
Sept 2002 |
ML022800398 |
| NUREG-1763 |
Differing Professional Views or Opinions 2002 Special Review Panel Report |
Sept 2002 |
ML022750569 |
| NUREG/CR-6775 |
Human Performance Characterization in the Reactor Oversight Process |
Sept 2002 |
ML022680488 |
| NUREG-1757 V2 DFC |
Consolidated NMSS Decommissioning Guidance: Characterization, Survey,
and Determination of Radiological Criteria (Draft for Comment) |
Sept 2002 |
ML022630021 |
| NUREG-1757 V1 |
Consolidated NMSS Decommissioning Guidance: Decommissioning Process
for Material Licensees (Final) |
Sept 2002 |
ML022620303 |
| NUREG-1623 |
Design of Erosion Protection for Long-Term Stabilization (Final) |
Sept 2002 |
ML022530043 |
| NUREG/BR-0297 |
NRC Public Meetings |
Aug 2002 |
ML030140334 |
| NUREG-1423 V12 |
A Compilation of Reports of The Advisory Committee on Nuclear
Waste: July 2001-June 2002 |
Aug 2002 |
ML022630589 |
| NUREG-1125 V23 |
A Compilation of Reports of The Advisory Committee on Reactor
Safeguards: 2001 Annual |
Aug 2002 |
ML022630640 |
| NUREG/CR-6777 |
Results and Analysis of The ASTM Round Robin On Reconstitution |
Aug 2002 |
ML022540225 |
| NUREG/CR-6772 |
GSI-191: Separate-Effects Characterization of Debris Transport in Water |
Aug 2002 |
ML022410104 |
| NUREG/CR-6771 |
GSI-191: The Impact of Debris Induced Loss of ECCS Recirculation on PWR
Core Damage Frequency |
Aug 2002 |
ML022410135 |
| NUREG/CR-6770 |
Thermal-Hydraulic Response of PWR Reactor Coolant System &
Containments to Selected Accident Sequences |
Aug 2002 |
ML022490254 |
| NUREG/CR-6690 V2 |
The Effects of Interface Management Tasks On Crew Performance and Safety
in Complex, Computer-Based Systems: Detailed Analysis |
Aug 2002 |
ML022540832 |
| NUREG/CR-6690 V1 |
The Effects of Interface Management Tasks On Crew Performance and Safety
in Complex, Computer-Based Systems: Overview and Main Findings |
Aug 2002 |
ML022520381 |
| NUREG/CR-6787 |
Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless
Steels in LWR Environments |
Aug 2002 |
ML022530013 |
| NUREG/CR-6787 Errata |
Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless
Steels in LWR Environments |
May 2005 |
ML051540104 |
| NUREG/CR-6762 V4 |
GSI-191Technical Assessment: Development of Debris Transport Fractions
In Support of the Parametric Evaluation |
Aug 2002 |
ML022480262 |
| NUREG/CR-6762 V3 |
GSI-191Technical Assessment: Development of Debris Generation Quantities
In Support of the Parametric Evaluation |
Aug 2002 |
ML022480182 |
| NUREG/CR-6762 V2 |
GSI-191Technical Assessment: Summary and Analysis of U.S. Pressurized
Water Reactor Industry Survey Responses and Responses to GL 97-04 |
Aug 2002 |
ML022470093 |
| NUREG/CR-6762 V1 |
GSI-191Technical Assessment: Parametric Evaluations for Pressurized Water
Reactor Recirculation Sump Performance |
Aug 2002 |
ML022470077 |
| NUREG-0936 V21 N1 |
NRC Regulatory Agenda: Semiannual Report January-June 2002 |
Aug 2002 |
ML022340368 |
| NUREG/CR-6782 DFC |
Comparison of U. S. Military and International Electromagnetic Compatibility
Guidance (Draft for Comment) |
July 2002 |
ML022340590 |
| NUREG-1761 DFC |
Radiological Surveys for Controlling Release of Solid Materials (Draft for
Comment) |
July 2002 |
ML022320121 |
| NUREG-1762 |
Integrated Issue Resolution Status Report |
July 2002 |
ML022240204 |
| NUREG/CR-6511 V8 |
Steam Generator Tube Integrity Program, Annual Report, October 1998 -
September 1999 |
July 2002 |
ML022180830 |
| NUREG/CR-5609 DFC |
Electromagnetic Compatibility Testing For Conducted Susceptibility Along
Interconnecting Signal Lines (Draft for Comment) |
July 2002 |
ML022320054 |
| NUREG/CR-6784 |
Use of Computerized Microtomography to Examine the Relationships of
Sorption Sites in Alluvial Soils to Iron and Pore Space Distributions |
July 2002 |
ML022110406 |
| NUREG/IA-0207 |
RELAP5/MOD3.2.2 Gamma Assessment for Down to Top Reflooding
Process at VVER Like 37-Rod Bundle |
July 2002 |
ML022110038 |
| NUREG/IA-0208 |
Analysis of the VTI Test Data on the Behavior of the Heated Rod
Temperatures in the Partially Uncovered VVER-440 Core Model Using
RELAP5/MOD3.2.2 Gamma |
July 2002 |
ML022060114 |
| NUREG/CR-5500 V11 |
Reliability Study: Babcock & Wilcox Reactor Protection System, 1984-1998 |
July 2002 |
ML022050241 |
| NUREG/CR-5500 V10 |
Reliability Study: Combustion Engineering Reactor Protection System,
1984-1998 |
July 2002 |
ML022060194 |
| NUREG/CP-0152 V4 |
Proceedings of Seventh NRC/ASME Symposium on Valve & Pump Testing
Held at Renaissance Washington DC Hotel Washington, DC July 15-18, 2002 |
July 2002 |
ML021970140 |
| NUREG/CR-6776 |
Cable Insulation Resistance Measurements Made During Cable Fire Tests |
June 2002 |
ML022600316 |
| NUREG-0980 V2 N6 |
Nuclear Regulatory Legislation" 107th Congress: 1st Session |
June 2002 |
ML022420144 |
| NUREG-0980 V1 N6 |
Nuclear Regulatory Legislation" 107th Congress: 1st Session |
June 2002 |
ML022410233 |
| NUREG-1758 |
Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray
Fires, International Panel Report |
June 2002 |
ML022310303 |
| NUREG/CR-6780 |
Effects of Adsorption Constant Uncertainty on Containment Plume Migration:
One- and Two-Dimensional Numerical Studies |
June 2002 |
ML022000164 |
| NUREG-1720 DFC |
Re-evaluation of the Indoor Resuspension Factor for the Screening Analysis of
the Building Occupancy Scenario for NRC's License Termination Rule
(Draft for Comment) |
June 2002 |
ML021830071 |
| NUREG-1437 S10 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Peach Bottom Atomic Power Station, Units 2 & 3 (Draft for
Comment) |
June 2002 |
ML021700317 |
| NUREG/CR-6768 |
Spent Nuclear Fuel Transportation Package Performance Study Issues Report |
June 2002 |
ML021720648 |
| NUREG-1707 V4 |
Interagency Steering Committee on Radiation Standards: 2001 Annual Report |
June 2002 |
ML021700458 |
| NUREG/CR-6511 V9 |
Steam Generator Tube Integrity Program Semiannual Report October 1999 -
March 2000 |
June 2002 |
ML021680409 |
| NUREG/BR-0291 |
Reactor License Renewal, Preparing for Tomorrow's Safety Today |
May 2002 |
ML021960511 |
| NUREG/CR-6765 |
Development of Technical Basis for Leak-Before-Break Evaluation
Procedures |
May 2002 |
ML021720594 |
| NUREG-0700 R2 |
Human-System Interface Design Review Guidelines |
May 2002 |
ML021700373 |
| NUREG/CP-0177 |
Proceedings of the Environmental Software Systems Compatibility and
Linkage Workshop - March 7-9, 2000 |
May 2002 |
ML021630189 |
| NUREG/CP-0176 |
Proceedings of the Nuclear Safety Research Conference Held at Marriott Hotel
at Metro Center Washington, DC, October 22-24, 2001 |
May 2002 |
ML021710837 |
| NUREG-0711 R1 |
Human Factors Engineering Program Review Model |
May 2002 |
ML021560629 |
| NUREG/CR-6764 |
Burnup Credit PIRT Report |
May 2002 |
ML021510370 |
| NUREG/CR-6756 |
Analysis of Potential for Jet-Impingement Erosion from Leaking Steam
Generator Tubes During Severe Accidents |
May 2002 |
ML021510332 |
| NUREG/CR-6774 |
Validation on Failure & Leak-Rate Correlations for Stress Corrosion Cracks in
Steam Generator Tubes |
May 2002 |
ML021510286 |
| NUREG-1760 |
Aging Assessment of Safety-Related Fuses Used in Low- & Medium-Voltage
Applications in Nuclear Power Plants |
May 2002 |
ML021360517 |
| NUREG-1437 S8 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding McGuire Nuclear Station, Units 1 and 2 (Draft for
Comment) |
May 2002 |
ML021270554 |
| NUREG-1437 S9 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Catawba Nuclear Station Units 1 & 2 (Draft for Comment) |
May 2002 |
ML021350561 |
| NUREG-1650 Add 1 |
The United States of America National Report for the Convention on Nuclear
Safety: Answers to Questions From the Peer Review By Contracting Parties -
April 2002 |
May 2002 |
ML021500670 |
| NUREG/CR-6769 |
Technical Basis for Revision of Regulatory Guidance on Design Ground
Motions: Development of Hazard- & Risk-Consistent Seismic Spectra for Two
Sites. |
April 2002 |
ML021440322 |
| NUREG/CR-6763 |
Aging Assessment of Safety-Related Fuses Used in Low- and Medium-
Voltage Applications in Nuclear Power Plants |
April 2002 |
ML021150375 |
| NUREG-1759 S1 |
Safety Evaluation Report Related to License Renewal of Turkey Point Nuclear
Plant, Units 3 & 4 |
April 2002 |
ML021560094 |
| NUREG/CR-6711 DFC |
Draft Environmental Assessment of Major Revision of 10 CFR Part 71 (Draft
for Comment) |
April 2002 |
ML021350459 |
| NUREG/CR-6712 |
Summary and Categorization of Public Comments on the Major Revision of
10CFR Part 71 |
April 2002 |
ML021350317 |
| NUREG/CR-6713 DFC |
Draft Regulatory Analysis of Major Revision of 10 CFR Part 71 Proposed
Rule |
April 2002 |
ML021350493 |
| NUREG-1753 |
Risk-Based Performance Indicators: Results of Phase 1 Development |
April 2002 |
ML021140546 |
| NUREG/CR-6767 |
Evaluation of Hydrologic Uncertainty Assessments for Decommissioning Sites
Using Complex & Simplified Models |
April 2002 |
ML021330273 |
| NUREG-1742 V1 |
Perspectives Gained From Individual Plant Examination of External Events
(IPEEE) Program |
April 2002 |
ML021270132 |
| NUREG-1742 V2 |
Perspectives Gained From Individual Plant Examination of External Events
(IPEEE) Program - Tables |
April 2002 |
ML021270674 |
| NUREG-1437 S6 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding Surry Power Station Units 1 and 2; (Draft for Comment) |
April 2002 |
ML021090402 |
| NUREG-1437 S7 DFC |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants Regarding North Anna Power Station, Units 1 and 2 (Draft for
Comment) |
April 2002 |
ML021270588 |
| NUREG/CR-4667 V31 |
Environmentally Assisted Cracking in Light Water Reactors, Semi-annual
Report, July 2000 - December 2000 |
April 2002 |
ML021270504 |
| NUREG-0090 V24 |
Report to Congress on Abnormal Occurrences, Fiscal Year 2001 |
April 2002 |
ML021050299 |
| NUREG/BR-0294 |
Visit NRC's Redesigned Web Site |
March 2002 |
ML030140382 |
| NUREG/CR-6669 |
Evaluation of Terminated Licenses Parts 30, 40, and 70: The Terminated
License Tracking System |
March 2002 |
ML021070409 |
| NUREG/CR-6766 |
Release of Radionuclides and Chelating Agents from Full-System
Decontamination Ion-Exchange Resins |
March 2002 |
ML021000623 |
| NUREG/CR-6042 R2 |
Perspectives on Reactor Safety |
March 2002 |
ML021080422 |
| NUREG/CR-6441 |
Analysis of Spent Fuel Heatup Following Loss of Water in a Spent Fuel Pool,"
Final Report |
March 2002 |
ML021050336 |
| NUREG-0654 R1 Add |
Criteria for Preparation & Evaluation of Radiological Emergency Response
Plans & Preparedness in Support of Nuclear Power Plants (Final) |
March 2002 |
ML021050240 |
| NUREG-1556 V9 DFC |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Medical Use Licenses (Revised Draft for Comment) |
March 2002 |
ML020980416 |
| NUREG/CR-6751 |
The Human Performance Evaluation Process: A Resource for Reviewing the
Identification & Resolution of Human Performance Problems |
March 2002 |
ML020930054 |
| NUREG-1520 |
Standard Review Plan for the Review of a License Application for a Fuel
Cycle Facility |
March 2002 |
ML020930033 |
| NUREG/CR-6753 |
Review of Findings for Human Performance Contribution to Risk in Operation
Events |
March 2002 |
ML020930077 |
| NUREG/CR-6500 R2 |
Owners of Nuclear Power Plants |
March 2002 |
ML020800542 |
| NUREG/CR-6761 |
Parametric Study of Effect of Burnable Poison Rods for PWR Burnup Credit |
March 2002 |
ML020770329 |
| NUREG-1804 R2 DFC |
Yucca Mountain Review Plan (Draft for Comment) |
March 2002 |
ML020770528 |
| NUREG/CR-6760 |
Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit |
March 2002 |
ML020770436 |
| NUREG/CR-6759 |
Parametric Study of Effect of Control Rods for PWR Burnup Credit |
Feb 2002 |
ML020810111 |
| NUREG-1542 V7 |
Performance & Accountability Report Fiscal Year 2001 |
Feb 2002 |
ML020810169 |
| NUREG/CR-6758 |
Radionuclide-Chelating Agent Complexes in Low-Level Radioactive
Decontamination Waste; Stability, Adsorbtion and Transportation Potential |
Feb 2002 |
ML020740582 |
| NUREG/CR-6757 |
Large-Scale Molecular Dynamics Simulations of Metal Sorption onto Basal
Surfaces of Clay Minerals |
Feb 2002 |
ML020660065 |
| NUREG/CR-6755 |
Technical Basis for Calculating Radiation Doses for the Building Occupancy
Scenario Using the Probabilistic RESRAD-BUILD 3.0 Code |
Feb 2002 |
ML020590035 |
| NUREG/CR-6632 |
Solubility and Leaching of Radionuclides in Site Decommissioning
Management Plan (SDMP) Slags |
Feb 2002 |
ML020530349 |
| NUREG-1100 V18 |
Budget Estimates and Performance Plan Fiscal Year 2003 |
Feb 2002 |
ML020390281 |
| NUREG-0386, Digest 11 |
United States Nuclear Regulatory Commission Staff Practice and Procedure
Digest: Commission, Appeal Board & Licensing Board Decisions July 1972 -
June 2001 |
Jan 2002 |
ML020600069 |
| NUREG-1756 |
Safety Culture: A Survey of the State-of-the-Art |
Jan 2002 |
ML020520006 |
| NUREG-1725 |
Human Interaction With Reused Soil: A Literature Search (Final) |
Jan 2002 |
ML020500432 |
| NUREG-0936 V20 N2 |
NRC Regulatory Agenda: Semiannual Report July - December 2001 |
Jan 2002 |
ML020440110 |
| NUREG/CR-6752 |
A Comparative Analysis Of Special Treatment Requirements For Systems,
Structures, And Components (SSCs) Of Nuclear Power Plants With
Commercial Requirements Of Non-Nuclear Power Plants |
Jan 2002 |
ML020330051 |
| NUREG-1755 |
Some Observations On Risk-Informing Appendices A & B to 10 CFR Part 50 |
Jan 2002 |
ML020380039 |
| NUREG-1757 V1 DFC |
Consolidated NMSS Decommissioning Guidance (Draft for Comment) |
Jan 2002 |
ML020380319 |
| NUREG-1437 S5 |
Generic Environmental Impact Statement for License Renewal of Nuclear
Plants, Regarding Turkey Point Units 3 & 4, (Final) |
Jan 2002 |
ML020280236 |
| NUREG-1650 |
The United States of America National Report for the Convention on Nuclear
Safety |
Jan 2002 |
ML020280291 |
| NUREG-1569 R1 DFC |
Standard Review Plan for In Situ Leach Uranium Extraction License
Applications (Draft for Comment) |
Jan 2002 |
ML020320348 |
| NUREG-1620 R1 DFC |
Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings
Sites Under Title II of the Uranium Mill Tailings Radiation Control Act (Draft
for Comment) |
Jan 2002 |
ML020320210 |
| NUREG/CR-6754 |
Review of Industry Responses to NRC Generic Letter 97-06 on Degradation of
Steam Generator Internals |
Dec 2001 |
ML020240392 |
| NUREG-1752 |
Assessment of Modernization and Integration of BWR Components and
Spatial Kinetics in the TRAC-M Version 3690 Code |
Dec 2001 |
ML020180129 |
| NUREG/CP-0175 |
Proceedings of the Advisory Committee on Reactor Safeguards Workshop on
Future Reactors |
Dec 2001 |
ML020100275 |
| NUREG/CR-6744 |
Phenomenon Identification and Ranking Tables (PIRTs) for Loss-of-Coolant
Accidents in Pressurized and Boiling Water Reactors Containing High Burnup
Fuel |
Dec 2001 |
ML013540628 |
| NUREG-1803 |
Safety Evaluation Report Related to the License Renewal of the Edwin I.
Hatch Nuclear Plant, Units 1 & 2 |
Dec 2001 |
ML020020307 |
| NUREG-1754 |
A Comparative Analysis of LWR Fuel Designs |
Dec 2001 |
ML013650469 |
| NUREG-1556 V1 R1 |
Consolidated Guidance About Material License: Program-Specific Guidance
About Portable Gauge Licenses (Final) |
Nov 2001 |
ML013650210 |
| NUREG-1556 V1 R1 Eratta |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Portable Gauge Licenses, Appendix H (Errata) |
July 2005 |
ML052130055 |
| NUREG-1736 |
Consolidated Guidance: 10 CFR Part 20 Standards for Protection Against
Radiation (Final Report) |
Nov 2001 |
ML013330179 |
| NUREG-1713 DFC |
Standard Review Plan for Decommissioning Cost Estimates for Nuclear
Power Reactors (Draft for Comment) |
Nov 2001 |
ML013240031 |
| NUREG/CR-6750 |
Performance of MOV Stem Lubricants at Elevated Temperature |
Oct 2001 |
ML020150282 |
| NUREG-1538 |
Preliminary Performance-Based Analyses Relevant to Dose-Based
Performance Measures for Proposed Geologic Repository at Yucca Mountain |
Oct 2001 |
ML013650319 |
| NUREG-0586 S1 DFC |
Generic Environmental Impact Statement on Decommissioning of Nuclear
Facilities: Draft Supplement Dealing with Decommissioning of Nuclear
Power Reactors (Draft for Comment) |
Oct 2001 |
ML013090387 |
| NUREG/CR-6728 |
Technical Basis for Revision of Regulatory Guidance on Design Ground
Motions: Hazard- and Risk- Consistent Ground Motion Spectra Guidelines |
Oct 2001 |
ML013100232 |
| NUREG/CR-6748 |
STARBUCS: A Prototypic SCALE Control Module for Automated Criticality
Safety Analyses Using Burnup Credit |
Oct 2001 |
ML013060098 |
| NUREG/CR-6747 |
Computational Benchmark for Estimation of Reactivity Margin from Fission
Products and Minor Actinides in PWR Burnup Credit |
Oct 2001 |
ML013060035 |
| NUREG/CP-0174 |
Transactions of the Twenty-Ninth Nuclear Safety Research
Conference (formerly The Water Reactor Safety Information Meeting) |
Oct 2001 |
ML012900154 |
| NUREG-1423 V11 |
A Compilation of Reports of The Advisory Committee on Nuclear Waste |
Sept 2001 |
ML013100347 |
| NUREG/CR-6746 |
Advanced Nondestructive Evaluation for Steam Generator Tubing |
Sept 2001 |
ML013060081
ML031340434
w/Errata |
| NUREG/CR-6745 |
Dry Cask Storage Characterization Project - Phase 1: CASTOR V/21 Cask
Opening and Examination |
Sept 2001 |
ML013020363 |
| NUREG/BR-0282 R1 |
Nuclear Research Programs To Ensure Public Health and Safety |
Sept 2001 |
ML012960273 |
| NUREG-0713 V22 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and
Other Facilities 2000 |
Sept 2001 |
ML012960275 |
| NUREG/CR-6739 V2 |
FRAPTRAN: Integral Assessment |
Sept 2001 |
ML012960311 |
| NUREG/CR-6714 |
Hanford Tank Waste Remediation System Pretreatment Chemistry &
Technology |
Sept 2001 |
ML012690529 |
| NUREG/CR-6742 |
Phenomenon Identification and Ranking Tables (PIRTs) for Rod Ejection
Accidents in Pressurized Water Reactors Containing High Burnup Fuel |
Sept 2001 |
ML012890487 |
| NUREG/CR-6115 |
PWR and BWR Pressure Vessel Fluence Calculation Benchmark Problems
and Solutions |
Sept 2001 |
ML012900043 |
| NUREG-1749 |
Implications From The Phenomenon Identification and Ranking Tables
(PIRTs) and Suggested Research Activities for High Burnup Fuel |
Sept 2001 |
ML012920504 |
| NUREG/CR-6743 |
Phenomenon Identification and Ranking Tables (PIRTs) for Power
Oscillations Without Scram in Boiling Water Reactors Containing High
Burnup Fuel |
Sept 2001 |
ML012850324 |
| NUREG-1750 |
Assessment of Soil Amplification of Earthquake Ground Motion Using the
"CARES" Code Version 1.2 |
Sept 2001 |
ML012840125 |
| NUREG/CR-6733 |
A Baseline Risk-Informed, Performance-Based Approach for In Situ Leach
Uranium Extraction Licensees |
Sept 2001 |
ML012840152 |
| NUREG-1748 DFC |
Environmental Review Guidance for Licensing Actions Associated With
NMSS Programs [Draft for Comment and Interim Use] |
Sept 2001 |
ML012840089 |
| NUREG-1802 V1 |
Role and Direction of Nuclear Regulatory Research: Summary of Expert
Panel Report |
Sept 2001 |
ML012760230 |
| NUREG-1802 V2 |
Role and Direction of Nuclear Regulatory Research: Expert Panel Report |
Sept 2001 |
ML012760301 |
| NUREG/CR-6119 V3 |
MELCOR Computer Code Manuals - Demonstration Problems Version 1.8.5
May 2001 |
Sept 2001 |
ML012670311 |
| NUREG/CR-6740 |
Structural Seismic Fragility Analysis of the Zion Containment |
Sept 2001 |
ML012610253 |
| NUREG/CR-6625 Add1 |
Automated Seismic Event Monitoring System |
Sept 2001 |
ML012620454 |
| NUREG/CR-6737 |
Bases for Predicting the Earliest Penetrations Due to SCC for Alloy 600 on the
Secondary Side of PWR Steam Generators |
Sept 2001 |
ML012610214 |
| NUREG/CR-6738 |
Risk Methods Insights Gained From Fire Incidents |
Sept 2001 |
ML012600429 |
| NUREG-0430 V20 |
Licensed Fuel Facility Status Report: Inventory Difference Data July 1999 -
June 2000 |
Sept 2001 |
ML012500423 |
| NUREG/BR-0137 R4 |
Fact Sheet: Nuclear Materials Safety and Safeguards |
Aug 2001 |
ML030130010 |
| NUREG-1746 |
System-Level Repository Sensitivity Analyses, Using TPA Version 3.2 Code |
Aug 2001 |
ML012990126 |
| NUREG/CR-6741 DFC |
Application of Microprocessor-Based Equipment In Nuclear Power Plants -
Technical Basis For A Qualification Methodology (Draft for Comment) |
Aug 2001 |
ML012600340 |
| NUREG-6739 V1 |
FRAPTRAN: A Computer Code for the Transient Analysis of Oxide Fuel
Rods |
Aug 2001 |
ML012530260 |
| NUREG/CR-5632 |
Incorporating Aging Effects into Probabilistic Risk Assessment - A Feasibility
Study Utilizing Reliability Physics Models |
Aug 2001 |
ML012490206 |
| NUREG-1747 |
Overview & Summary of NRC Involvement with DOE in Tank Waste
Remediation System-Privatization (TWRS-P) Program |
Aug 2001 |
ML012390250 |
| NUREG/CR-6732 |
Zinc-Zircaloy Interaction in Dry Storage Casks |
Aug 2001 |
ML012330333 |
| NUREG/CR-6735 |
Effects of Deregulation on Safety: Implications Drawn From The Aviation,
Rail and United Kingdom Nuclear Power Industries |
Aug 2001 |
ML012390333 |
| NUREG-0936 V20 N1 |
NRC Regulatory Agenda: Semiannual Report January - June 2001 |
Aug 2001 |
ML012330144 |
| NUREG/CR-6729 |
Field Studies for Estimating Uncertainties in Ground-Water Recharge Using
Near-Continuous Peizometer Data. |
July 2001 |
ML012260250 |
| NUREG/CR-6730 V1 |
TRAC-M/F77, Version 5.5 Developmental Assessment Manual: Assessment |
July 2001 |
ML012260328 |
| NUREG/CR-6730 V2 |
TRAC-M/F77, Version 5.5 Developmental Assessment Manual: Appendices |
July 2001 |
ML012210362 |
| NUREG/CR-6734 V1 |
Digital Systems Software Requirements Guidelines: Guidelines |
July 2001 |
ML012330160 |
| NUREG/CR-6734 V2 |
Digital Systems Software Requirements Guidelines: Failure Descriptions |
July 2001 |
ML012330184 |
| NUREG/CR-6720 |
TRAC-M Validation Test Matrix |
July 2001 |
ML012210126 |
| NUREG/CR-6719 |
Assessment of the Relevance of Displacement Bases Design Methods/Criteria
to Nuclear Plant Structures |
July 2001 |
ML012140454 |
| NUREG/IA-0203 |
Assessment of RELAP5/MOD3.2.2y Against Flooding Database in
Horizontal-to-Inclined Pipes |
July 2001 |
ML012130047 |
| NUREG-1800 |
Standard Review Plan for Review of License Renewal Applications for
Nuclear Power Plant |
July 2001 |
ML012070413 |
| NUREG-1739 |
Analysis of Public Comments on the Improved License Renewal Guidance
Documents |
July 2001 |
ML012080104 |
| NUREG-1801 V1 |
Generic Aging Lessons Learned (GALL) Report: Summary |
July 2001 |
ML012060392 |
| NUREG-1801 V2 |
Generic Aging Lessons Learned (GALL) Report: Tabulation of Results |
July 2001 |
ML012060545 |
| NUREG/CR-6724 |
TRAC-M/FORTRAN 90 Version 3.0 Theory Manual |
July 2001 |
ML012000277 |
| NUREG/CP-0173 |
International Collaborative Project to Evaluate Fire Models for Nuclear Power
Plant Applications: Summary of 2nd Meeting |
July 2001 |
ML011970240 |
| NUREG-0933 S25 |
A Prioritization of Generic Safety Issues |
June 2001 |
ML012190431 |
| NUREG-1745 |
Standard Format and Content for Technical Specifications for 10 CFR Part 72
Cask Certificates of Compliance |
June 2001 |
ML011940387 |
| NUREG-0800 Ch 19 R1
DFC |
Proposed Revision 1 to Standard Review Plan Chapter 19: Use of
Probabilistic Risk Assessment in Plant-Specific, Risk-Informed
Decisionmaking: General Guidance (Draft for Comment) |
June 2001 |
ML011940192 |
| NUREG/CR-4667 V30 |
Environmentally Assisted Cracking In Light Water Reactors |
June 2001 |
ML011780497 |
| NUREG-1434 V1 R2 |
Standard Technical Specifications General Electric Plants,
BWR/6: Specifications |
June 2001 |
ML011780537 |
| NUREG-1434 V2 R2 |
Standard Technical Specifications General Electric Plants, BWR/6: Bases |
June 2001 |
ML011780675 |
| NUREG-1433 V1 R2 |
Standard Technical Specifications General Electric Plants,
BWR/4: Specifications |
June 2001 |
ML011780639 |
| NUREG-1433 V2 R2 |
Standard Technical Specifications General Electric Plants, BWR/4: Bases |
June 2001 |
ML011780553 |
| NUREG-1432 V1 R2 |
Standard Technical Specifications Combustion Engineering
Plants: Specifications |
June 2001 |
ML011930335 |
| NUREG-1432 V2 R2 |
Standard Technical Specifications Combustion Engineering Plants: Bases |
June 2001 |
ML011930508 |
| NUREG-1431 V1 R2 |
Standard Technical Specifications Westinghouse Plants: Specifications |
June 2001 |
ML011840223 |
| NUREG-1431 V2 R2 |
Standard Technical Specifications Westinghouse Plants: Bases |
June 2001 |
ML011840412 |
| NUREG-1430 V1 R2 |
Standard Technical Specifications Babcock and Wilcox Plants:
Specifications |
June 2001 |
ML011770186 |
| NUREG-1430 V2 R2 |
Standard Technical Specifications Babcock and Wilcox Plants: Bases |
June 2001 |
ML011770313 |
| NUREG-1707 V3 |
Interagency Steering Committee on Radiation Standards: 2000 Annual Report |
June 2001 |
ML011690196 |
| NUREG-1635 V4 |
Review and Evaluation of the Nuclear Regulatory Commission Safety
Research Program |
May 2001 |
ML011710324 |
| NUREG/CR-6725 |
TRAC-M/FORTRAN 90 (Version 3.0) Programmer's Manual |
May 2001 |
ML011650648 |
| NUREG-0525 V4 |
Annual Safeguards Summary Event List (SSEL) : January 1 Through
December 31, 2000 |
May 2001 |
ML011650322 |
| NUREG/CR-6722 |
TRAC-M/FORTRAN 90 (Version 3.0) User's Manual |
May 2001 |
ML011510082 |
| NUREG-1743 |
Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear
One, Unit 1: Docket No. 50-313 |
May 2001 |
ML011640298 |
| NUREG-1744 |
Assessment of the TRAC-M Codes Using Flecht-Seaset Reflood and Steam
Cooling Data |
May 2001 |
ML011520327 |
| NUREG/CR-6717 |
Environmental Effects on Fatigue Crack Initiation in Piping and Pressure
Vessel Steels |
May 2001 |
ML011450101 |
| NUREG-1513 |
Integrated Safety Analysis Guidance Document |
May 2001 |
ML011440260 |
| NUREG-1125 V22 |
The Advisory Committee on Reactor Safeguards: 2000 Annual |
April 2000 |
ML011710380 |
| NUREG/IA-0202 |
Analyses of KS Test Data on the Heated Rod Bundle Temperature Behavior in
RBMK-1500 Core Model Under Stop and Recovery Flow Using
RELAP5/M0D3.2 and RELAP5/MOD3.2.2 GAMMA |
April 2001 |
ML011440156 |
| NUREG/IA-0199 |
Mechanical Properties of Unirradiated and Irradiated Zr-1% Nb Cladding -
Procedures and Results of Low Temperature Biaxial Burst Tests and axial
Tensile Tests |
April 2001 |
ML011440098 |
| NUREG/CP-0172 |
Proceedings of the Twenty-Eighth Water Reactor Safety Information Meeting |
April 2001 |
ML011370638 |
| NUREG/CR-6715 |
Probability-Based Evaluation of Degraded Reinforced Concrete Components
in Nuclear Power Plants |
April 2001 |
ML011280259 |
| NUREG-1742 V1 DFC |
Perspectives Gained From The Individual Plant Examination of External
Events (IPEEE) Program [Draft for Comment] |
April 2001 |
ML011210524 |
| NUREG/CR-6718 |
OPUS/PlotOPUS: An ORIGEN-S Post-Processing Utility and Plotting
Program for SCALE |
April 2001 |
ML011170333 |
| NUREG-0090 V23 |
Report to Congress on Abnormal Occurrences: Fiscal Year 2000 |
April 2001 |
ML011170060 |
| NUREG/CR-6721 |
Effects of Alloy Chemistry, Cold Work, and Water Chemistry on Corrosion
Fatigue and Stress Corrosion Cracking of Nickel Alloys and Welds |
April 2001 |
ML011170079 |
| NUREG-1021 R8 S1 |
Operator Licensing Examination Standards for Power Reactors |
April 2001 |
ML011080036 |
| NUREG-1100 V17 |
Budget Estimates and Performance Plan: Fiscal Year 2002 |
April 2001 |
ML011000248 |
| NUREG/CR-5512 V2 |
Residual Radioactive Contamination From Decommissioning: User's Manual
DandD Version 2.1 |
April 2001 |
ML010940257 |
| NUREG/CR-6707 |
Seismic Analysis of a Reinforced Concrete Containment Vessel Model |
March 2001 |
ML011220269 |
| NUREG/BR-0053 R5 |
USNRC Regulations Handbook |
March 2001 |
ML011010202 |
| NUREG/BR-0283 |
Region I Entry Level Inspector Qualification Program |
March 2001 |
ML011000022 |
| NUREG-1741 |
RASCAL 3.0: Description of Models and Methods |
March 2001 |
ML010940218 |
| NUREG/CR-6710 |
Extending the Dynamic Flowgraph Methodology (DFM) to Model Human
Performance and Team Effects |
March 2001 |
ML010960107 |
| NUREG-1542 V6 |
U.S. NRC Performance and Accountability Report: Fiscal Year 2000 |
March 2001 |
ML010870527 |
| NUREG/CR-6708 |
Surface Complexation Modeling of Uranium (VI) Adsorption on Natural
Mineral Assemblages |
March 2001 |
ML010880205 |
| NUREG/IA-0201 |
Description and RELAP5 Assessment of the PMK-2 CAMP-CLB
Experiment: 2% Cold Leg Break Without HPIS With Secondary Bleed |
March 2001 |
ML010860212 |
| NUREG/IA-0200 |
Assessment Study on the PMK-2 Total Loss of Feedwater Experiment Using
RELAP5 Code |
March 2001 |
ML010860240 |
| NUREG/CR-6716 |
Recommendations on Fuel Parameters for Standard Technical Specifications
for Spent Fuel Storage Casks |
March 2001 |
ML010820352 |
| NUREG/CR-6584 V1 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment:
Description of Experiment and Summary of Results |
March 2001 |
ML010740249 |
| NUREG/CR-6584 V2 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment:
Geotechnical Site Characterization Review |
March 2001 |
ML010790049 |
| NUREG/CR-6584 V3 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Results
of the Forced Vibration Tests |
March 2001 |
ML010790073 |
| NUREG/CR-6584 V4 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Response
of the Model to Seismic Events |
March 2001 |
ML010740298 |
| NUREG-1740 |
Voltage-Based Alternative Repair Criteria |
March 2001 |
ML010750315 |
| NUREG/CR-6706 |
Capacity of Steel & Concrete Containment Vessels with Corrosion Damage |
Feb 2001 |
ML011070123 |
| NUREG/BR-0282 |
Nuclear Research Programs To Ensure Public Health and Safety |
Feb 2001 |
ML010820370 |
| NUREG/CR-6695 |
Hydrologic Uncertainty Assessment For Decommissioning
Sites: Hypothetical Test Case Applications |
Feb 2001 |
ML010670139 |
| NUREG-0654 R1
Addenda DFC |
Criteria for Preparation and Evaluation of Radiological Emergency Response
Plans and Preparedness in Support of Nuclear Power Plants: Draft for
Comment |
Feb 2001 |
ML010660136 |
| NUREG-1668 V1 |
NRC Sensitivity and Uncertainty Analyses for a Proposed HLW Repository at
Yucca Mountain, Nevada Using TPA 3.1: Conceptual Models and Data |
Feb 2001 |
ML010660124 |
| NUREG/IA-0198 |
Assessment of RELAP5/MOD3 With the SNUF Test Simulating Hot Leg
Break LOCA in the View of Mass and Energy Release Analysis |
Feb 2001 |
ML010590239 |
| NUREG/GR-0020 |
Embedded Digital System Reliability and Safety Analyses |
Feb 2001 |
ML010570243 |
| NUREG/CR-6696 |
LAPUR 5.2 Verification and User's Manual |
Feb 2001 |
ML010320049 |
| NUREG/CR-6704 V1 |
Assessment of Environmental Qualification Practices and Condition
Monitoring Techniques for Low-Voltage Electric Cables: LOCA Test Results |
Feb 2001 |
ML010510387 |
| NUREG/CR-6704 V2 |
Assessment of Environmental Qualification Practices and Condition
Monitoring Techniques for Low-Voltage Electric Cables: Condition
Monitoring Test Results |
Feb 2001 |
ML010460247 |
| NUREG/CR-6705 |
Historical Case Analysis of Uranium Plume Attenuation |
Feb 2001 |
ML010460162 |
| NUREG/CR-6666 |
Survey of Waste Solidification Process Technologies |
Feb 2001 |
ML010460184 |
| NUREG-0936 V19 N2 |
NRC Regulatory Agenda: Semiannual Report July - December 2000 |
Feb 2001 |
ML010450228 |
| NUREG/CR-6597 |
Results and Insights on the Impact of Smoke on Digital Instrumentation and
Control |
Jan 2001 |
ML011090023 |
| NUREG/IA-0197 |
Assessment of RELAP5/MOD3.2-NPA3.4 Against an Inadvertent Closure of
all Three MSIV's in VANDELLOS-II Nuclear Power Plant |
Jan 2001 |
ML010370161 |
| NUREG/CR-6703 |
Environmental Effects of Extending Fuel Burnup Above 60 Gwd/MTU |
Jan 2001 |
ML010310298 |
| NUREG/CR-6700 |
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms
Related to Transport and Interim Storage of High-Burnup LWR Fuel |
Jan 2001 |
ML010330186 |
| NUREG/IA-0195 |
LBLOCA Analysis in a Westinghouse PWR 3-Loop Design Using
RELAP5/MOD3 |
Jan 2001 |
ML010330385 |
| NUREG/CR-0041 R1 |
Manual of Respiratory Protection Against Airborne Radioactive Material |
Jan 2001 |
ML010310331 |
| NUREG/CR-6150 V1 R2 |
SCDAP/RELAP5/MOD 3.3 Code Manual: Code Architecture and Interface
of Thermal Hydraulic and Core Behavior Models |
Jan 2001 |
ML010310283 |
| NUREG/CR-6150 V2 R2 |
SCDAP/RELAP5/MOD 3.3 Code Manual: Modeling of Reactor Core and
Vessel Behavior During Severe Accidents |
Jan 2001 |
ML010370328 |
| NUREG/CR-6150 V3 R2 |
SCDAP/RELAP5/MOD 3.3 Code Manual: User's Guide and Input Manual |
Jan 2001 |
ML010310311 |
| NUREG/CR-6150 V4 R2 |
SCDAP/RELAP5/MOD 3.3 Code Manual: MATPRO - A Library of
Materials Properties for Light-Water-Reactor Accident Analysis |
Jan 2001 |
ML010330424 |
| NUREG/CR-6150 V5 R2 |
SCDAP/RELAP5/MOD 3.3 Code Manual: Assessment of Modeling of
Reactor Core Behavior During Severe Accidents |
Jan 2001 |
ML010310397 |
| NUREG/IA-0196 |
Analysis of PANDA Experiments P3 and P6 Using RELAP5/MOD3.2 |
Jan 2001 |
ML010310235 |
| NUREG/IA-0194 |
Analysis of Inadvertent Pressurizer Spray Valve Opening Real Transient with
RELAP5/MOD3.2 |
Jan 2001 |
ML010290286 |
| NUREG/IA-0193 |
Assessment of Single Recirculation Pump Trip Transient in Santa Maria de
Garona Nuclear Power Plant With TRAC-BF1/MOD1, Version 0.4 |
Jan 2001 |
ML010290321 |
| NUREG/IA-0192 |
Assessment of RELAP5/MOD3.2.2 Gamma With the LOFT L9-3 Experiment
Simulating an Anticipated Transient Without Scram |
Jan 2001 |
ML010240063 |
| NUREG/CR-6701 |
Review of Technical Issues Related to Predicting Isotopic Compositions and
Source Terms for High-Burnup LWR Fuel |
Jan 2001 |
ML010230244 |
| NUREG/CR-6699 |
A Review of Large-Scale Fracture Experiments Relevant to Pressure Vessel
Integrity Under Pressurized Thermal Shock Conditions |
Jan 2001 |
ML010170101 |
| NUREG/CR-6702 |
Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8
and Current International Practice |
Jan 2001 |
ML010190276 |
| NUREG/CR-6698 |
Guide for Validation of Nuclear Criticality Safety Calculational Methodology |
Jan 2001 |
ML010170125 |
| NUREG/CR-6577 S1 |
U.S. Nuclear Power Plant Operating Cost and Experience Summaries |
Jan 2001 |
ML010120458 |
| NUREG/IA-0191 |
A Tool for Drawing With Excel |
Jan 2001 |
ML010120460 |
| NUREG/BR-0280 |
Producing Nuclear Fuel |
Dec 2000 |
ML010250280 |
| NUREG-1556 V20 |
Consolidated Guidance About Materials Licenses: Guidance About
Administrative Licensing Procedures (Final) |
Dec 2000 |
ML010250252 |
| NUREG-1556 V12 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Possession Licenses for Manufacturing and Distribution
(Final) |
Dec 2000 |
ML010230297 |
| NUREG-1737 |
Software Quality Assurance Procedures for NRC Thermal Hydraulic Codes |
Dec 2000 |
ML010170081 |
| NUREG/CR-6119 V1 R2 |
MELCOR Computer Code Manuals: Primer and User's Guide Version 1.8.5 |
Dec 2000 |
ML010120463 |
| NUREG/CR-6119 V2 R2 |
MELCOR Computer Code Manuals: Reference Manuals Version 1.8.5 |
Dec 2000 |
ML010190466 |
| NUREG-1556 V16 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Licenses Authorizing Distribution to General
Licensees (Final) |
Dec 2000 |
ML010120151 |
| NUREG/CR-6697 |
Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0
Computer Codes |
Dec 2000 |
ML010090284 |
| NUREG-1556 V10 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Master Materials Licenses (Final) |
Dec 2000 |
ML010110251 |
| NUREG-1556 V19 |
Consolidated Guidance About Materials Licenses: Guidance for Agreement
State Licensees About NRC Form 241 "Report of Proposed Activities in
Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore
Waters" and Guidance For NRC Licensees Proposing to Work in Agreement
State Jurisdiction (Reciprocity) (Final) |
Dec 2000 |
ML003781280 |
| NUREG/CR-6694 |
POLIDENT: A Module for Generating Continuous-Energy Cross Sections
From ENDF Resonance Data |
Dec 2000 |
ML003774026 |
| NUREG/CR-4667 V29 |
Environmentally Assisted Cracking in Light Water Reactors
Semiannual Report (July 1999 - December 1999) |
Nov 2000 |
ML003777632 |
| NUREG-1556 V18 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Service Provider Licenses (Final) |
Nov 2000 |
ML003779351 |
| NUREG-1556 V15 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Changes of Control and About Bankruptcy Involving
Byproduct, Source, or Special Nuclear Material Licences (Final) |
Nov 2000 |
ML003778305 |
| NUREG/BR-0164 R4 |
NRC Regulator of Nuclear Safety |
Nov 2000 |
ML003776974 |
| NUREG-1556 V17 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Special Nuclear Material of Less Than Critical Mass
Licenses (Final) |
Nov 2000 |
ML003776996 |
| NUREG/CR-6629 |
Atom Probe Tomography Characterization of the Solute Distributions in a
Neutron-Irradiated and Annealed Pressure Vessel Steel Weld |
Nov 2000 |
ML003775237 |
| NUREG/GR-0019 |
Software Engineering Measures for Predicting Software Reliability in Safety
Critical Digital Systems |
Nov 2000 |
ML003775310 |
| NUREG/CR-6609 |
Comparison of Irradiation-Induced Shifts of Kjc and Charpy Impact
Toughness for Reactor Pressure Vessel Steels |
Nov 2000 |
ML003774072 |
| NUREG/IA-0137 |
A Study of Control Room Staffing Levels for Advanced Reactors |
Nov 2000 |
ML003774060 |
| NUREG/CR-6692 |
Probabilistic Modules for the RESRAD and RESRAD-BUILD Computer
Codes: User Guide |
Nov 2000 |
ML003774030 |
| NUREG/CR-5736 |
Evaluation of WF-70 Weld Metal From the Midland Unit 1 Reactor Vessel |
Nov 2000 |
ML003771165 |
| NUREG/CR-6628 |
The Effects of Aging at 343C on the Microstructure and Mechanical
Properties of Type 308 Stainless Steel Weldments |
Nov 2000 |
ML003773653 |
| NUREG-0383 V2 R23 |
Directory of Certificates of Compliance for Radioactive Materials Packages
(Certificates of Compliance) |
Nov 2000 |
ML003771317 |
| NUREG-0383 V3 R20 |
Directory of Certificates of Compliance for Radioactive Materials Packages
(Report of NRC-Approved Quality Assurance Programs for Radioactive
Materials Packages) |
Nov 2000 |
ML003770603 |
| NUREG/CR-6691 |
The Effects of Alarm Display, Processing, and Availability on Crew
Performance |
Nov 2000 |
ML003770890 |
| NUREG/CR-6684 |
Advanced Alarm Systems: Revision of Guidance and Its Technical Basis |
Nov 2000 |
ML003770903 |
| NUREG-1275 V14 |
Causes and Significance of Design-Based Issues at U.S. Nuclear Power Plants |
Nov 2000 |
ML003770985 |
| NUREG/CR-6686 |
Experience With the Scale Criticality Safety Cross-Section Libraries |
Oct 2000 |
ML003770016 |
| NUREG-1573 |
A Performance Assessment Methodology For Low-Level Radioactive Waste
Disposal Facilities: Recommendations of NRC's Performance Assessment
Working Group |
Oct 2000 |
ML003770778 |
| NUREG/BR-0117 #00-2 |
NMSS Licensee Newsletter Jun - July 2000 |
Oct 2000 |
ML003766433 |
| NUREG/BR-0117 #00-3 |
NMSS Licensee Newsletter Sept - Oct 2000 |
Oct 2000 |
ML003769528 |
| NUREG/CR-6685 |
Pretest Analysis of a 1:4-Scale Prestressed Concrete Containment Vessel
Model |
Oct 2000 |
ML003768645 |
| NUREG/CR-6688 |
Testing, Verifying, and Validating SAPHIRE Versions 6.0 and 7.0 |
Oct 2000 |
ML003768858 |
| NUREG/IA-0190 |
Nowadays Tools for Graphical Post-Processing of TRAC-BF1 Results |
Oct 2000 |
ML003768533 |
| NUREG-1511 S2 |
Reactor Pressure Vessel Status Report |
Oct 2000 |
ML003766056 |
| NUREG-0713 V21 |
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and
Other Facilities 1999: Thirty-Second Annual Report |
Oct 2000 |
ML003765709 |
| NUREG/CR-6687 |
Irradiation-Assisted Stress Corrosion Cracking of Model Austenitic Stainless
Steel Alloys |
Oct 2000 |
ML003763797 |
| NUREG-1022 R2 |
Event Reporting Guidelines 10 CFR 50.72 and 50.73 |
Oct 2000 |
ML003762595 |
| NUREG/CR-6689 |
Proposed Approach for Reviewing Changes to Risk-Important Human Actions |
Oct 2000 |
ML003764744 |
| NUREG/CP-0171 |
Transactions of the Twenty-Eighth Water Reactor Safety Information Meeting |
Oct 2000 |
ML003761621 |
| NUREG/IA-0189 |
Improvements of RELAP5/MOD3.2.2 Models for the CANDU Plant Analysis |
Oct 2000 |
ML003762564 |
| NUREG/CR-6679 |
Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants |
Sept 2000 |
ML003751396 |
| NUREG-1423 V10 |
A Compilation of Report of The Advisory Committee on Nuclear Waste July 1999 - June 2000 |
Sept 2000 |
ML003766667 |
| NUREG-1736 DFC |
Consolidated Guidance About Materials Licenses: Consolidated Guidance:
Standards for Protection Against Radiation in 10 CFR Part 20 (Draft for
Comment) |
Sept 2000 |
ML003766447 |
| NUREG/BR-0215 R1 |
Public Involvement in the Nuclear Regulatory Process |
Sept 2000 |
ML003762531 |
| NUREG-1727 |
NMSS Decommissioning Standard Review Plan |
Sept 2000 |
ML003761169 |
| NUREG-1614 V2 P1 |
U.S. Nuclear Regulatory Commission Strategic Plan Fiscal Years 2001 -
2005: Main Report |
Sept 2000 |
ML003761640 |
| NUREG-1614 V2 P2 |
U.S. Nuclear Regulatory Commission Strategic Plan Fiscal Years 2001 -
2005: Appendix |
Sept 2000 |
ML003755413 |
| NUREG-1307 R9 |
Report on Waste Burial Charges: Changes in Decommissioning Waste
Disposal Cost at Low-Level Waste Burial Facilities |
Sept 2000 |
ML003757577 |
| NUREG/CR-6682 |
Summary and Categorization of Public Comments on the Control of Solid
Materials |
Sept 2000 |
ML003754410 |
| NUREG/CR-6511 V7 |
Steam Generator Tube Integrity Program: Semiannual Report October 1998 -
March 1999 |
Sept 2000 |
ML003752483 |
| NUREG-0430 V19 |
Licensed Fuel Facility Status Report: Inventory Difference Data July 1998 -
June 1999 |
Sept 2000 |
ML003745753 |
| NUREG/CR-6683 |
A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to
Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel
Pool Storage |
Sept 2000 |
ML003751298 |
| NUREG-1575 R1 |
Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) |
Aug 2000 |
ML003761476 |
| NUREG/BR-0256 |
The U.S. Nuclear Regulatory Commission and How It Works |
Aug 2000 |
ML003749551 (tiff)
ML031400642 (pdf) |
| NUREG/BR-0249 R1 |
The Atomic Safety Licensing Board Panel |
Aug 2000 |
ML003755820 |
| NUREG/CR-6567 |
Low-Level Radioactive Waste Classification, Characterization, and
Assessment: Waste Streams and Neutron-Activated Metals |
Aug 2000 |
ML003752437 |
| NUREG/CR-6471 V2 |
Characterization of Flaws in U.S. Reactor Pressure Vessels: Validation of
Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel |
Aug 2000 |
ML003754908 |
| NUREG/GR-0018 |
Dating of Liquefaction Features in the New Madrid Seismic Zone |
Aug 2000 |
ML003752771 |
| NUREG/CR-6679 |
Assessment of Age-Related Degradation of Structures and Passive
Components for U.S. Nuclear Power Plants |
Aug 2000 |
ML003751396 |
| NUREG/CR-6664 |
Pressure and Leak-Rate Tests and Models for Predicting Failure of Flawed
Steam Generator Tubes |
Aug 2000 |
ML003749701 |
| NUREG-1707 V2 |
Interagency Steering Committee on Radiation Standards: 1999 Annual Report |
Aug 2000 |
ML003749714 |
| NUREG/IA-0188 |
RELAP5/MOD3.2 Validation Using BETHSY Test 6.9a |
Aug 2000 |
ML003743672 |
| NUREG/IA-0187 |
RELAP5/MOD3 Analysis of BETHSY Test 6.9c: Loss of RHRS: SG Manway
Open |
Aug 2000 |
ML003743436 |
| NUREG-0936 V19 N1 |
NRC Regulatory Agenda: Semiannual Report January - June 2000 |
Aug 2000 |
ML003743679 |
| NUREG/CR-6678 |
Pretest Round Robin Analysis of a Prestressed Concrete Containment Vessel
Model |
Aug 2000 |
ML003745890 |
| NUREG/CR-6680 |
Review Templates for Computer-Based Reactor Protection Systems |
Aug 2000 |
ML003745748 |
| NUREG/CR-6681 |
Ampacity Derating and Cable Functionality for Raceway Fire Barriers |
Aug 2000 |
ML003745784 |
| NUREG/BR-0050 R2 |
ACNW 2000 Action Plan |
Aug 2000 |
ML003743100 |
| NUREG-1718 |
Standard Review Plan for the Review of an Application for a Mixed Oxide
(MOX) Fuel Fabrication Facility: Final Report |
Aug 2000 |
ML003741587 |
| NUREG/CP-0152 V13 |
Proceedings of the Sixth NRC/ASME Symposium on Valve and Pump Testing |
July 2000 |
ML003733511 |
| NUREG/CR-6676 |
Probabilistic Dose Analysis Using Parameter Distributions Developed For
RESRAD and RESRAD-BUILD Codes |
July 2000 |
ML003741920 |
| NUREG/BR-0058 R3 |
Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission
Final Report July 2000 (Re-scanned Nov. 2002 due to missing figure) |
July 2000 |
ML023290519 |
| NUREG/CR-6647 |
Adsorption and Desorption Behavior of Selected 10 CFR Part 61
Radionuclides From Ion Exchange Resin by Waters of Different Chemical
Composition |
July 2000 |
ML003739007 |
| NUREG-1709 |
Selection of Sample Rate and Computer Wordlength in Digital
Instrumentation and Control Systems |
July 2000 |
ML003737890 |
| NUREG-1556 V19 DFC |
Consolidated Guidance About Materials Licenses: Guidance for Agreement
State Licensees About NRC Form 241 "Report of Proposed Activities in
Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore
Waters" and Guidance For NRC Licensees Proposing to Work in Agreement
State Jurisdiction (Reciprocity) (Draft for Comment) |
July 2000 |
ML003737386 |
| NUREG-1649 R3 |
Reactor Oversight Process |
July 2000 |
ML003738931 |
| N/CR-6677 |
Evaluation Of Risk Associated With Intergranular Stress Corrosion Cracking
In Boiling Water Reactor Internals |
July 2000 |
ML003736113 |
| NUREG/CR-4674 V27 |
Precursors to Potential Severe Core Damage Accidents: 1998 A Status Report |
July 2000 |
ML003733843 |
| NUREG-1556 V20 DFC |
Consolidated Guidance About Materials Licenses: Guidance About
Administrative Licensing Procedures (Draft for Comment) |
July 2000 |
ML003732000 |
| NUREG/IA-0186 |
Analysis of the RELAP5/MOD3.2.2beta Critical Flow Models and
Assessment Against Critical Flow Data From the Marviken Tests |
July 2000 |
ML003733356 |
| NUREG/CR-6662 |
KENO3D Visualization Tool for KENO V .a and KENO-VI Geometry
Models |
June 2000 |
ML003739075 |
| NUREG/CR-4667 V28 |
Environmentally Assisted Cracking in Light Water Reactors
Semiannual Report January 1999-June 1999 |
June 2000 |
ML003733883 |
| NUREG-1724 DFC |
Standard Review Plan for the Review of DOE Plans for Achieving Regulatory
Compliance at Sites With Contaminated Ground Water Under Title I of the
Uranium Mill Tailings Radiation Control Act (Draft for Comment) |
June 2000 |
ML003731007 |
| NUREG/IA-0180 |
Application of RELAP5/MOD3.1 to ATWS Analysis of Control Rod
Withdrawal From 1% Power Level |
June 2000 |
ML003734249 |
| NUREG-0940 V18 N2 P1 |
Enforcement Actions: Significant Actions Resolved Individual Actions
Semiannual Progress Report July-December 1999 |
June 2000 |
ML003730011 |
| NUREG-0940 V18 N2 P2 |
Enforcement Actions: Significant Actions Resolved Reactor Licensees
Semiannual Progress Report July-December 1999 |
June 2000 |
ML003729814 |
| NUREG-0940 V18 N2 P3 |
Enforcement Actions: Significant Actions Resolved Material Licensees
Semiannual Progress Report July-December 1999 |
June 2000 |
ML003729792 |
| NUREG-1556 V14 |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Well Logging, Tracer, and Field Flood Study Licenses |
June 2000 |
ML003729920 |
| NUREG-0386 Digest 10 |
U.S. Nuclear Regulatory Commission Staff Practice and Procedure Digest:
July 1972 - December 1998 |
June 2000 |
ML003731308 |
| NUREG-0040 V23 N3 |
Licensee Contractor and Vendor Inspection Status Report
Quarterly Report July - September 1999 |
June 2000 |
ML003728263 |
| NUREG-0040 V23 N4 |
Licensee Contractor and Vendor Inspection Status Report
Quarterly Report October-December 1999 |
June 2000 |
ML003729839 |
| NUREG/CR-6650 |
PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup
Covariance Matrices |
June 2000 |
ML003730951 |
| NUREG/IA-0183 |
Analysis of the LOBI Experiment Test BT-56 Using the RELAP5/MOD3.2
Code |
June 2000 |
ML003729779 |
| NUREG-1714 DFC |
Environment Impact Statement for the Construction and Operation of an
Independent Spent Fuel Storage Installation on the Reservation of the Skull
Valley Band of Goshute Indians and the Related Transportation Facility in
Tooele County, Utah (Draft for Comment) |
June 2000 |
ML003725097 |
| NUREG-1628 |
Staff Responses to Frequently Asked Questions Concerning Decommissioning
of Nuclear Power Plants |
June 2000 |
ML003726190 |
| NUREG-1725 DFC |
Human Interaction With Reused Soil: A Literature Search (Draft for
Comment) |
June 2000 |
ML003731948 |
| NUREG-1715 V2 |
Component Performance Study-Motor-Driven Pumps, 1987-1998 Commercial
Power Reactors |
June 2000 |
ML003726139 |
| NUREG/IA-0185 |
Development and Validation of a Transition Boiling Model for the
RELAP5/MOD3 Reflood Simulation |
June 2000 |
ML003727954 |
| NUREG/CR-6675 |
Interaction of Zinc Vapor with Zircaloy and the Effect of Zinc Vapor on the
Mechanical Properties of Zircaloy |
June 2000 |
ML003727961 |
| NUREG/IA-0184 |
In-Tube Steam Condensation in the Presence of Air |
June 2000 |
ML003727967 |
| NUREG-1620 |
Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings
Sites Under Title II of the Uranium Mill Tailings Radiation Control Act |
June 2000 |
ML003725860 |
| NUREG-1726 |
Predictions of Spent Fuel Heatup After a Complete Loss of Spent Fuel Pool
Coolant |
June 2000 |
ML003727905 |
| NUREG/CR-6673 |
Hydrogen Generation in TRU Waste Transportation Packages |
May 2000 |
ML003723404 |
| NUREG/CR-6667 |
Standard Review Plan for Safeguards Contingency Response Plans for
Category I Fuel Facilities |
May 2000 |
ML003718179 |
| NUREG/CR-0200 V1 P1
R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Control Modules C4, C6 |
May 2000 |
ML003721266 |
| NUREG/CR-0200 V1 P2
R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Control Modules D1, S1-S5,
H1 |
May 2000 |
ML003721371 |
| NUREG/CR-0200 V2 P1
R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Functional Models F1 - F8 |
May 2000 |
ML003722257 |
| NUREG/CR-0200 V2 P2
R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Functional Models F9 - F11 |
May 2000 |
ML003722444 |
| NUREG/CR-0200 V2 P3
R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Functional Models F16 - F17 |
May 2000 |
ML003722168 |
| NUREG/CR-0200 V3 R6 |
SCALE Ver 4.4: A Modular Code System for Performing Standardized
Computer Analyses for Licensing Evaluation-- Miscellaneous M1 - M17 |
May 2000 |
ML003722537 |
| NUREG-1556 V18 DFC |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Service Provider Licenses (Draft for Comment) |
May 2000 |
ML003721589 |
| NUREG-1624 R1 |
Technical Basis and Implementation Guidelines for A Technique for Human
Event Analysis (ATHEANA) |
May 2000 |
ML003719212
ML003719239 |
| NUREG-1719 |
Pipe Cracking in U.S. BWRs: A Regulatory History |
May 2000 |
ML003719804 |
| NUREG/CR-6668 |
Standard Review Plan for Training and Qualifications Plans for Security
Personnel at Category I Fuel Facilities |
May 2000 |
ML003719803 |
| NUREG-1600 |
General Statement of Policy and Procedure for NRC Enforcement Actions |
May 2000 |
ML003715971 |
| NUREG/BR-0276 |
Reference for Regulatory Guidance Applicable to License Transfers |
Apr 2000 |
ML062220055 |
| NUREG-0525 V3 |
Annual Safeguards Summary Event List (SSEL) 1999 |
Apr 2000 |
ML003720139 |
| NUREG/BR-0217 R1 |
The Regulation and Use of Radioisotopes In Today's World |
Apr 2000 |
ML003718172 |
| NUREG-1125 V21 |
A Compilation of Reports of The Advisory Committee on Reactor Safeguards:
1999 Annual |
Apr 2000 |
ML003717297 |
| NUREG/CR-6653 |
Comparison of Estimated Ground-Water Recharge Using Different Temporal
Scales of Field Data |
Apr 2000 |
ML003711159 |
| NUREG-1712 |
Nuclear Byproduct Material Risk Review |
Apr 2000 |
ML003711063 |
| NUREG-1700 |
Standard Review Plan for Evaluating Nuclear Power Reactor License
Termination |
Apr 2000 |
ML003713038 |
| NUREG/IA-0182 |
Application of RELAP5/MOD3.2 to the Loss-of-Residual-Heat-Removal
Event Under Shutdown Condition |
Apr 2000 |
ML003714398 |
| NUREG-1715 V1 |
Component Performance Study - Turbine-Driven Pumps, 1987-1998
Commercial Power Reactors |
Apr 2000 |
ML003708823 |
| NUREG/CR-6342 |
Fracture Toughness Testing With Cracked Round Bars: Feasibility Study |
Apr 2000 |
ML003709956 |
| NUREG/IA-0181 |
Assessment of RELAP5/MOD3.2 for Reflux Condensation Experiment |
Apr 2000 |
ML003709858 |
| NUREG-1669 |
A Risk Analysis of Fixed Nuclear Gauges |
Apr 2000 |
ML003709930 |
| NUREG/CP-0170 |
International Collaborative Project to Evaluate Fire Models for Nuclear Power
Plant Applications: Summary of Planning Meeting |
Apr 2000 |
ML003706118 |
| NUREG/CR-5591 V8 N2 |
Heavy-Section Steel Irradiation Program: Progress Report Apr 1997 - Mar
1998 |
Apr 2000 |
ML003708030 |
| NUREG/CR-6427 |
Assessment of the DCH Issue for Plants with Ice Condenser Containments |
Apr 2000 |
ML003712849 |
| NUREG/CR-6214 R1 |
Production and Testing of the Revised VITAMIN-B6 Fine-Group and the
BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived
From END/B-VI.3 Nuclear Data |
Apr 2000 |
ML003708920 |
| NUREG-1717 DFC |
Systematic Radiological Assessment of Exemptions for Source and Byproduct
Materials (Draft for Comment) |
Mar 2000 |
ML003700964 |
| NUREG-1635 V3 |
Review and Evaluation of the Nuclear Regulatory Commission Safety
Research Program |
Mar 2000 |
ML003713468 |
| NUREG/CR-6500 R1 |
Owners of Nuclear Power Plants |
Mar 2000 |
ML003695075 |
| NUREG/IA-0176 |
Post-Test Analysis of P5 Experiment in PANDA Facility With TRAC-BF1
Code |
Mar 2000 |
ML003695388 |
| NUREG/IA-0177 |
Assessment of a Reactor Coolant Pump Trip for TRILLO NPP with
RELAP5/MOD3.2 |
Mar 2000 |
ML003695419 |
| NUREG-1617 |
Standard Review Plan for Transportation Packages for Spent Nuclear Fuel |
Mar 2000 |
ML003696262 |
| NUREG/IA-0179 |
A Standardized Methodology for the Linkage of Computer Codes:
Application to RELAP5/MOD3.2 |
Mar 2000 |
ML003696288 |
| NUREG-1702 |
Standard Review Plan for the Review of a License Application for the Tank
Waste Remediation System Privatization (TWRS-P) Project |
Mar 2000 |
ML003696360 |
| NUREG/CR-6672 V1 |
Reexamination of Spent Fuel Shipment Risk Estimates- Main Report |
Mar 2000 |
ML003698324 |
| NUREG-1542 V5 |
Accountability and Performance Report: FY 1999 |
Mar 2000 |
ML003700182 |
| NUREG-1555 V1 |
Environmental Standard Review Plan: Chapters 1 - 4 |
Mar 2000 |
ML003702134 |
| NUREG-1555 V2 |
Environmental Standard Review Plan: Chapters 5 - 10 and Appendices |
Mar 2000 |
ML003701937 |
| NUREG-1555 V1 S1 |
Environmental Standard Review Plan- Supplement 1: Operating License
Renewal |
Mar 2000 |
ML003702019 |
| NUREG/CR-5741 |
Technical Bases for Regulatory Guide for Soil Liquefaction |
Mar 2000 |
ML003701612 |
| NUREG-1556 V17 DFC |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Special Nuclear Material of Less Than Critical Mass Licenses (Draft
for Comment) |
Mar 2000 |
ML003700214 |
| NUREG/CR-6633 |
Advanced Information Systems Design: Technical Basis and Human Factors
Review Guidance |
Mar 2000 |
ML003704877 |
| NUREG/CR-6634 |
Computer-Based Procedure Systems: Technical Basis and Human Factors
Review Guidance |
Mar 2000 |
ML003704853 |
| NUREG/CR-6635 |
Soft Controls: Technical Basis and Human Factors Review Guidance |
Mar 2000 |
ML003705030 |
| NUREG/CR-6636 |
Maintainability of Digital Systems: Technical Basis and Human Factors
Review Guidance |
Mar 2000 |
ML003705072 |
| NUREG/CR-6637 |
Human Systems Interface and Plant Modernization Process: Technical Basis
and Human Factors Review Guidance |
Mar 2000 |
ML003705052 |
| NUREG/IA-0178 |
Cofrentes NPP (BWR/6) ATWS (MSIVC) Analysis with TRAC-BF1 |
Mar 2000 |
ML003695409 |
| NUREG/IA-0175 |
Analysis of Pin-by-Pin Effects for LWR Rod Ejection Accident |
Mar 2000 |
ML003692574 |
| NUREG-1567 |
Standard Review Plan for Spent Fuel Dry Storage Facilities |
Mar 2000 |
ML003686776 |
| NUREG-1723 |
Safety Evaluation Report Related to the License Renewal of Oconee Nuclear
Station: Units 1, 2 & 3 |
Mar 2000 |
ML003695154 |
| NUREG-1614 V2 P1 DFC |
USNRC Strategic Plan FY 2000 - 2005: Main Report (Draft for Comment) |
Mar 2000 |
ML003692570 |
| NUREG-1614 V2 P2 DFC |
USNRC Strategic Plan FY 2000 - 2005: Appendix (Draft for Comment) |
Mar 2000 |
ML003692582 |
| NUREG/BR-0046 R29 |
NRC Telephone Directory |
Mar 2000 |
ML003726120 |
| NUREG/CR-5679 |
Design, Instrumentation and Testing of a Steel Containment Vessel Model |
Mar 2000 |
ML003693055 |
| NUREG-0090 V22 |
Report to Congress on Abnormal Occurrences: Fiscal Year 1999 |
Feb 2000 |
ML003688154 |
| NUREG-0936 V18 N2 |
NRC Regulatory Agenda Semiannual Report July - December 1999 |
Feb 2000 |
ML003685256 |
| NUREG-1275 V13 |
Evaluation of Air-Operated Valves at U.S. Light-Water Reactors |
Feb 2000 |
ML003691726 |
| NUREG/CR-6654 |
A Study of Air-Operated Valves in U.S. Nuclear Power Plants |
Feb 2000 |
ML003691872 |
| NUREG/CR-6431 |
Recommended Electromagnetic Operating Envelopes for Safety-Related I&C
Systems in Nuclear Power Plants |
Jan 2000 |
ML003706139 |
| NUREG/CR-5739 |
Laboratory Investigations of Soils and Rocks For Engineering Analysis and
Design of Nuclear Power Facilities |
Jan 2000 |
ML003686696 |
| NUREG/CR-6638 |
Advanced NDE for Steam Generator Tubing |
Jan 2000 |
ML003686799 |
| NUREG-1556 V7 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Academic, Research and Development, and Other Licenses
of Limited Scope Including Gas Chromatographs and X-Ray Fluorescence
Analyers |
Dec 1999 |
ML010510258 |
| NUREG-0980 V1 N5 |
Nuclear Regulatory Legislation 105th Congress |
Dec 1999 |
ML003695650 |
| NUREG-0980 V2 N5 |
Nuclear Regulatory Legislation 105th Congress |
Dec 1999 |
ML003695782 |
| NUREG/CR-6651 |
International Comparative Assessment Study of Pressurized Thermal Shock in
Reactor Pressure Vessels |
Dec 1999 |
ML003726831 |
| NUREG/CR-6658 |
TRAC-M Programmer's Guide: Fortran 77 Version 5.5 |
Dec1999 |
ML003726328 |
| NUREG/CR-6648 |
Environmental Assessment: San Bernadino National Wildlife Refuge Well 10 |
Dec 1999 |
ML003734176 |
| NUREG/BR-0175 R1 |
A Short History of Nuclear Regulation 1946-1999 |
Dec 1999 |
ML003726170 |
| NUREG/IA-0170 |
RELAP5/MOD3.2 Post Test Calculation of the PKL-Experiment PKLIII-B4.3 |
Dec 1999 |
ML003726910 |
| NUREG/CR-6471 V3 |
Characterization of Flaws in U.S. Reactor Pressure Vessels |
Nov 1999 |
ML003727107 |
| NUREG/CR-5738 |
Field Investigations for Foundations of Nuclear Power Facilities |
Nov 1999 |
ML003726925 |
| NUREG/CR-6622 |
Probabilistic Liquefaction Analysis |
Nov 1999 |
ML003726834 |
| NUREG/CR-6624 |
Recommendations for Revision of Regulatory Guide 1.78 |
Nov 1999 |
ML003726870 |
| NUREG/CR-6655 V1 |
Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation:
Methods Development |
Nov 1999 |
ML003726900 |
| NUREG/CR-6655 V2 |
Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation:
Illustrative Applications and Initial Guidance |
Nov 1999 |
ML003726890 |
| NUREG/IA-0169 |
Analysis of KS-1 Experimental Data on the Behavior of the Heated Rod
Temperatures in the Partially Uncovered VVER Core Model Using
RELAP5/MOD3.2 |
Nov 1999 |
ML003726810 |
| NUREG-0430 V18 |
Licensed Fuel Facility Status Report: Inventory Difference Data July 1997 -
June 1998 |
Nov 1999 |
ML003774491 |
| NUREG/CR-6511 V6 |
Steam Generator Tube Integrity Program -- Annual Report October 1997 -
September 1998 |
Oct 1999 |
ML003726922 |
| NUREG/CR-4667 V27 |
Environmentally Assisted Cracking in Light Water Reactors |
Oct 1999 |
ML003726930 |
| NUREG/CR-5512 V4 |
Comparison of the Models and Assumptions Used in the DandD 1.0,
RESRAD 5.61, and RESRAD-Build 1.50 Computer Codes with Respect to the
Residential Farmer and Industrial Occupant Scenarios Provided in
NUREG/CR-5512 |
Oct 1999 |
ML003727263 |
| NUREG/CR-5512 V3 |
Residual Radioactive Contamination From Decommissioning Parameter
Analysis |
Oct 1999 |
ML003726967 |
| NUREG-1574 R1 DFC |
Standard Review Plan on Antitrust Reviews (Draft for Comment) |
Oct 1999 |
ML003726099 |
| NUREG/CR-6623 |
Vapor Explosions in a One-Dimensional Large Scale Geometry with Simulant
Melts |
Oct 1999 |
ML003726130 |
| NUREG/CP-0168 |
Transactions of the Twenty-Seventh Water Reactor Safety Information
Meeting |
Oct 1999 |
ML003726087 |
| NUREG-1556 V13 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Commercial Radiopharmacy Licenses (Final) |
Sept 1999 |
ML010370227 |
| NUREG/CR-6369 V1 |
Drywell Debris Transport Study |
Sept 1999 |
ML003728226 |
| NUREG/CR-6369 V2 |
Drywell Debris Transport Study: Experimental Work |
Sept 1999 |
ML003726871 |
| NUREG/CR-6369 V3 |
Drywell Debris Transport Study: Computational Work |
Sept 1999 |
ML003728322 |
| NUREG/CR-6572 V3 P1 |
Severe Accident Risks for VVER Reactors: The Kalinin PRA Program
Procedures Guide |
Sept 1999 |
ML003726112 |
| NUREG/BR-0137 R3 |
Fact Sheet: Nuclear Material Safety and Safeguards |
Aug 1999 |
ML003726176 |
| NUREG/IA-0156 V1 |
Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb
Cladding and UO2 Fuel (VVER Type) Under Reactivity Accident Conditions:
Review of Research program and Analysis of Results |
July 1999 |
ML061450606 |
| NUREG/IA-0156 V2 |
Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb
Cladding and UO2 Fuel (VVER Type) Under Reactivity Accident Conditions:
Description of Test Proceedures and Analytical Methods |
July 1999 |
ML061450531 |
| NUREG/IA-0156 V3 |
Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb
Cladding and UO2 Fuel (VVER Type) Under Reactivity Accident Conditions: |
July 1999 |
ML061530302 |
| NUREG-1556 V11 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Licenses of Broad Scope (Final) |
April 1999 |
ML010370193 |
| NUREG/BR-0075 R4 |
NRC Field Policy Manual |
March 1999 |
ML041170225 |
| NUREG-1556 V6 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About 10 CFR Part 36 Irradiator Licenses (Final) |
Jan 1999 |
ML010370137 |
| NUREG-0650 R2 |
Preparing NUREG-Series Publications |
Jan 1999 |
ML041050294 |
| NUREG/BR-0010 R3 |
Citizen's Guide to U.S Nuclear Regulatory Commission Information |
Dec 1998 |
ML003727043 |
| NUREG-1556 V5 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Self-Shielded Irradiator Licenses (Final) |
Oct 1998 |
ML010370198 |
| NUREG-1556 V3 |
Consolidated Guidance About Materials Licenses: Applications for Sealed
Source and Device Evaluation and Registration |
July 1998 |
ML010370028 |
| NUREG-1556 V2 |
Consolidated Guidance About Materials Licenses: Programs-Specific
Guidance About Industrial Radiography Licenses |
Aug 1998 |
ML010370172 |
| NUREG-1556 V2 Errata |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance
About Industrial Radiography Licenses, Appendix F (Eratta) |
July 2005 |
ML052130054 |
| NUREG/CR-6517 |
Round Robin Pretest Analyses of a Steel Containment Vessel Model and
Contact Structure Assembly Subject to Static Internal Pressurization |
Aug 1998 |
ML003727053 |
| NUREG-0544 R4 |
NRC Collection of Abbreviations |
July 1998 |
ML041050544 |
| NUREG-1496 V1 |
Generic Environmental Impact Statement in Support of Rulemaking on
Radiological Criteria for License Termination of NRC-Licensed Nuclear
Facilities - Main Report |
July 1997 |
ML042310492 |
| NUREG-1496 V2 |
Generic Environmental Impact Statement in Support of Rulemaking on
Radiological Criteria for License Termination of NRC-Licensed Nuclear
Facilities - |
July 1997 |
ML042320379 |
| NUREG-1496 V3 |
Generic Environmental Impact Statement in Support of Rulemaking on
Radiological Criteria for License Termination of NRC-Licensed Nuclear
Facilities - |
July 1997 |
ML042330385 |
| NUREG-1556 V1 |
Consolidated Guidance About Materials Licenses: Program-Specific
Guidance About Portable Gauge Licenses (Final Report) |
May 1997 |
ML010370104 |
| NUREG/CR-5512 V1 |
Residual Radioactive Contamination From Decommissioning |
Oct 1992 |
ML052220317 |
| NUREG/CR-5732 |
Iodine Chemical Forms in LWR Severe Accidents |
April 1992 |
ML003726825 |
| NUREG-1412 |
Foundation for the Adequacy of the Licensing Bases – A Supplement to the Statement of Considerations for the Rule on Nuclear Power Plant License Renewal (10 CFR Part 54) |
Dec 1991 |
ML080310668 |
| NUREG/CR-5737 |
Hydrogeologic Performance Assessment of the Commercial Low-Level
Radioactive Waste Disposal Facility Near West Valley, New York |
June 1991 |
ML003726086 |
| NUREG-1379 |
NRC Editorial Style Guide |
Oct 1989 |
ML041050307 |
| NUREG/BR-0111 |
Transporting Spent Fuel: Protection Provided Against Severe Highway and
Railroad Accidents |
Mar 1987 |
ML012360032 |
| NUREG-0654 R1 |
Criteria for Preparation & Evaluation of Radiological Emergency Response
Plans & Preparedness in Support of Nuclear Power Plants (Final) |
Nov 1980 |
ML040420012 |
