| 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 |