| Documents added January 1, 2000 through December 30, 2004 |
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/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-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/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 |
ML041550746 |
| NUREG-1350 V16 |
USNRC Information Digest 2004-2005 Edition |
Aug 2004 |
ML042230185 |
| NUREG-1021 R9 |
Operator Licensing Examination Standards for Power Reactors |
July 2004 |
ML042360006 |
| NUREG-1576 V1 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP): Chapters 1-9 and Appendix A-E |
July 2004 |
ML042320438 |
| NUREG-1576 V2 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP): Chapters 10-17 and Appendix F |
July 2004 |
ML042310547 |
| NUREG-1576 V3 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP): Chapters 18-20 and Appendix G |
July 2004 |
ML042310738 |
| 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 |
ML042320083 |
| 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 |
ML042300668 |
| 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 |
ML042300658 |
| 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 |
ML042300649 |
| NUREG-1792 DFC |
Good Practices for Implementing Human Reliability Analysis (Draft for Comment) |
July 2004 |
ML041550723 |
| 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 |
ML041980358 |
| NUREG/CR-6848 |
Preliminary Validation of a Methodology for Assessing Software Quality |
July 2004 |
ML024180117 |
| NUREG/CP-0185 |
Proceedings of the 2003 Nuclear Safety Research Conference |
July 2004 |
ML042170285 |
| NUREG/BR-0289 R2 |
Nuclear Power Plant Licensing Process |
July 2004 |
ML042050210 |
| NUREG/CP-0152 V5 |
Proceedings of the Eighth NRC/ASME Symposium on Valve and Pump Testing |
July 2004 |
ML042120007 |
| NUREG/CR-6846 |
Air Oxidation for Zr-Based Alloys |
July 2004 |
ML041900037 |
| 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 |
ML041900069 |
| 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 |
ML041880213 |
| 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 |
ML041910211 |
| NUREG-1434 V1 R3 |
Standard Technical Specifications: General Electric BWR/6 Plants - Specifications |
June 2004 |
ML041910046 |
| 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 V26 |
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 |
Mar 2004 |
ML041260323 |
| NUREG/BR-0168 R3 |
Guide for Information Technology Security: Policy for Processing Unclassified Safeguards Information (SGI) on NRC Computers |
Mar 2004 |
ML041130006 |
| NUREG-1787 |
Safety Evaluation Report Related to the License Renewal of Virgil C. Summer Nuclear Station, Unit 1 |
Mar 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 |
Mar 2004 |
ML040990584 |
| NUREG-1785 |
Safety Evaluation Report Related to the License Renewal of H.B. Robinson Steam Electric Plant, Unit 2 |
Mar 2004 |
ML040990702 |
| NUREG/CP-0184 |
Advisory Committee Nuclear Waste NRC/DOE Performance Assessments Workshop |
Mar 2004 |
ML040990484 |
| NUREG/BR-0309 |
Serving on the Advisory Committee on the Medical Uses of Isotopes (ACMUI) - A Member's Guide |
Mar 2004 |
ML040790351 |
| NUREG/CR-6817 |
A Generalized Procedure for Generating Flaw-Related Inputs for the FAVOR Code |
Mar 2004 |
ML040830499 |
| NUREG/BR-0298 R1 |
Nuclear Power Plant Licensing Process |
Mar 2004 |
ML040770057 |
| NUREG/CR-6682 S1 |
Summary and Categorization of Public Comments on Controlling the Disposition of Solid Materials |
Mar 2004 |
ML040720691 |
| 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-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/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 |
Mar 2003 |
ML031830555 |
| NUREG/CR-6810 |
Overpressurization Test of a 1:4 Scale Prestressed Concrete Containment Vessel Model |
Mar 2003 |
ML032040014 |
| NUREG/CR-6812 |
Emerging Technologies in Instrumentation and Controls |
Mar 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 |
Mar 2003 |
ML031060154 |
| NUREG/CR-6801 |
Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses |
Mar 2003 |
ML031110292 |
| NUREG-0383 V1 R24 |
Directory of Certificates of Compliance for Radioactive Materials Packages. Report of NRC-Approved Packages |
Mar 2003 |
ML031070542 |
| NUREG-0383 V2 R24 |
Directory of Certificates of Compliance for Radioactive Materials Packages, Certificates of Compliance |
Mar 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 |
Mar 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 |
Mar 2003 |
ML030850251 |
| NUREG-1769 |
Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 |
Mar 2003 |
ML031010136 |
| NUREG/CR-6799 |
Analysis of Rail Car Components Exposed to Tunnel Fire Environment |
Mar 2003 |
ML031050501 |
| NUREG/CR-6807 |
Results of NRC-Sponsored Stellite 6 Aging & Friction Testing |
Mar 2003 |
ML030850725 |
| NUREG/CR-6806 |
MOV Stem Lubricant Aging Research |
Mar 2003 |
ML030780590 |
| NUREG/CR-6800 |
Assessment of Reactivity Margins & Loading Curves for PWR Burnup-Credit Cask Designs |
Mar 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-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 - Mar 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 - Mar 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 |
Mar 2002 |
ML030140382 |
| NUREG/CR-6669 |
Evaluation of Terminated Licenses Parts 30, 40, and 70: The Terminated License Tracking System |
Mar 2002 |
ML021070409 |
| NUREG/CR-6766 |
Release of Radionuclides and Chelating Agents from Full-System Decontamination Ion-Exchange Resins |
Mar 2002 |
ML021000623 |
| NUREG/CR-6042 R2 |
Perspectives on Reactor Safety |
Mar 2002 |
ML021080422 |
| NUREG/CR-6441 |
Analysis of Spent Fuel Heatup Following Loss of Water in a Spent Fuel Pool," Final Report |
Mar 2002 |
ML021050336 |
| NUREG-0654 R1 Add |
Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants (Final) |
Mar 2002 |
ML021050240 |
| NUREG-1556 V9 DFC |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Medical Use Licenses (Revised Draft for Comment) |
Mar 2002 |
ML020980416 |
| NUREG/CR-6751 |
The Human Performance Evaluation Process: A Resource for Reviewing the Identification & Resolution of Human Performance Problems |
Mar 2002 |
ML020930054 |
| NUREG-1520 |
Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility |
Mar 2002 |
ML020930033 |
| NUREG/CR-6753 |
Review of Findings for Human Performance Contribution to Risk in Operation Events |
Mar 2002 |
ML020930077 |
| NUREG/CR-6500 R2 |
Owners of Nuclear Power Plants |
Mar 2002 |
ML020800542 |
| NUREG/CR-6761 |
Parametric Study of Effect of Burnable Poison Rods for PWR Burnup Credit |
Mar 2002 |
ML020770329 |
| NUREG-1804 R2 DFC |
Yucca Mountain Review Plan (Draft for Comment) |
Mar 2002 |
ML020770528 |
| NUREG/CR-6760 |
Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit |
Mar 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-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 |
Mar 2001 |
ML011220269 |
| NUREG/BR-0053 R5 |
USNRC Regulations Handbook |
Mar 2001 |
ML011010202 |
| NUREG/BR-0283 |
Region I Entry Level Inspector Qualification Program |
Mar 2001 |
ML011000022 |
| NUREG-1741 |
RASCAL 3.0: Description of Models and Methods |
Mar 2001 |
ML010940218 |
| NUREG/CR-6710 |
Extending the Dynamic Flowgraph Methodology (DFM) to Model Human Performance and Team Effects |
Mar 2001 |
ML010960107 |
| NUREG-1542 V6 |
U.S. NRC Performance and Accountability Report: Fiscal Year 2000 |
Mar 2001 |
ML010870527 |
| NUREG/CR-6708 |
Surface Complexation Modeling of Uranium (VI) Adsorption on Natural Mineral Assemblages |
Mar 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 |
Mar 2001 |
ML010860212 |
| NUREG/IA-0200 |
Assessment Study on the PMK-2 Total Loss of Feedwater Experiment Using RELAP5 Code |
Mar 2001 |
ML010860240 |
| NUREG/CR-6716 |
Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks |
Mar 2001 |
ML010820352 |
| NUREG/CR-6584 V1 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Description of Experiment and Summary of Results |
Mar 2001 |
ML010740249 |
| NUREG/CR-6584 V2 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Geotechnical Site Characterization Review |
Mar 2001 |
ML010790049 |
| NUREG/CR-6584 V3 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Results of the Forced Vibration Tests |
Mar 2001 |
ML010790073 |
| NUREG/CR-6584 V4 |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment: Response of the Model to Seismic Events |
Mar 2001 |
ML010740298 |
| NUREG-1740 |
Voltage-Based Alternative Repair Criteria |
Mar 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 343°C on the Microstructure and Mechanical Properties of Type 308 Stainless Steel Weldments |
Nov 2000 |
ML003773653 |
| NUREG-0383 V1 R23 |
Directory of Certificates of Compliance for Radioactive Materials Packages
(Report of NRC-Approved Packages) |
Nov 2000 |
ML003770726 |
| 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 - Mar 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-0304 V24 N2 |
Abstracts for Publications in the NUREG-Series: Annual Compilation for 1999 |
July 2000 |
ML003736630 |
| 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-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-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 |
Mar 1999 |
ML041140485 |
| 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 |
ML041050544 |
| 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/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 V |
Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Portable Gauge Licenses (Final Report) |
May 1997 |
ML010370104 |
| NUREG/CR-5732 |
Iodine Chemical Forms in LWR Severe Accidents |
April 1992 |
ML003726825 |
| NUREG/CR-5737 |
Hydrogeologic Performance Assessment of the Commercial Low-Level Radioactive Waste Disposal Facility Near West Valley, New York |
June 1991 |
ML003726086 |
