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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2001
| Documents added in 2001 | |||
|---|---|---|---|
| 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/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 (Package) |
| NUREG/CP-0175 | Proceedings of the Advisory Committee on Reactor Safeguards Workshop on Future Reactors | Dec 2001 | ML020100275 (Package) |
| 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 (Package) |
| NUREG-1803 | Safety Evaluation Report Related to the License Renewal of the Edwin I. Hatch Nuclear Plant, Units 1 & 2 | Dec 2001 | ML020020307 (Package) |
| 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 (Package) |
| 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 (Package) |
| NUREG-1538 | Preliminary Performance-Based Analyses Relevant to Dose-Based Performance Measures for Proposed Geologic Repository at Yucca Mountain | Oct 2001 | ML013650319 (Package) |
| 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 (Package) |
| 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 (Package) |
| 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 (Package) |
| 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 (Package) |
| 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-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 (Package) |
| 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 (Package) |
| 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/CR-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 (Package) |
| 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 (Package) |
| NUREG/CR-6730 V2 |
TRAC-M/F77, Version 5.5 Developmental Assessment Manual: Appendices | July 2001 | ML012210362 (Package) |
| 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 (Package) |
| 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 (Package) |
| NUREG-1739 | Analysis of Public Comments on the Improved License Renewal Guidance Documents | July 2001 | ML012080104 (Package) |
| 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 (Package) |
| NUREG/CR-6724 | TRAC-M/FORTRAN 90 Version 3.0 Theory Manual | July 2001 | ML012000277 (Package) |
| 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 (Package) |
| 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 (Package) |
| NUREG-1434 V2 R2 |
Standard Technical Specifications General Electric Plants, BWR/6: Bases | June 2001 | ML011780675 (Package) |
| NUREG-1433 V1 R2 |
Standard Technical Specifications General Electric Plants, BWR/4: Specifications | June 2001 | ML011780639 (Package) |
| NUREG-1433 V2 R2 |
Standard Technical Specifications General Electric Plants, BWR/4: Bases | June 2001 | ML011780553 (Package) |
| NUREG-1432 V1 R2 |
Standard Technical Specifications Combustion Engineering Plants: Specifications | June 2001 | ML011930335 (Package) |
| NUREG-1432 V2 R2 |
Standard Technical Specifications Combustion Engineering Plants: Bases | June 2001 | ML011930508 (Package) |
| NUREG-1431 V1 R2 |
Standard Technical Specifications Westinghouse Plants: Specifications | June 2001 | ML011840223 (Package) |
| NUREG-1431 V2 R2 |
Standard Technical Specifications Westinghouse Plants: Bases | June 2001 | ML011840412 (Package) |
| NUREG-1430 V1 R2 |
Standard Technical Specifications Babcock and Wilcox Plants: Specifications | June 2001 | ML011770186 (Package) |
| NUREG-1430 V2 R2 |
Standard Technical Specifications Babcock and Wilcox Plants: Bases | June 2001 | ML011770313 (Package) |
| 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 (Package) |
| 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 (Package) |
| NUREG-1743 | Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear One, Unit 1: Docket No. 50-313 | May 2001 | ML011640298 (Package) |
| 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 (Package) |
| NUREG/CR-6715 | Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants | April 2001 | ML011280259 (Package) |
| 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 (Package) |
| NUREG/BR-0053 R5 |
USNRC Regulations Handbook | March 2001 | ML011010202 (Package) |
| 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 | ML010520049 |
| 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 (Package) |
| 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-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 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026