| Document Identifier |
Title |
| NUREG-75/087 |
Standard Review Plan for the Review of Safety Analysis
Reports for Nuclear Power Plants |
| NUREG-0090 |
Report to Congress on Abnormal Occurrences |
| NUREG-0386 |
USNRC Staff Practice and Procedure Digest: Commission,
Appeal Board and Licensing Board Decisions |
| NUREG-0430 |
Licensed Fuel Facility Status Report: Inventory Difference
Data July 1, 2001 - June 30, 2002 |
| NUREG-0492 |
Fault Tree Handbook |
| NUREG-0544 |
NRC Collection of Abbreviations |
| NUREG-0586 |
Final Generic Environmental Impact Statement on Decommissioning
of Nuclear Facilities |
| NUREG-0612 |
Control of Heavy Loads at Nuclear Power Plants |
| NUREG-0654 |
Criteria for Preparation and Evaluation of Radiological
Emergency Response Plans and Preparedness in Support of Nuclear Power
Plants |
| NUREG-0696 |
Functional Criteria for Emergency Response Facilities |
| NUREG-0700 |
Human-System Interface Design Review Guidelines |
| NUREG-0711 |
Human Factors Engineering Program Review Model |
| NUREG-0713 |
Occupational Radiation Exposure at Commercial Nuclear
Power Reactors and Other Facilities |
| NUREG-0725 |
Public Information Circular
for Shipments of Irradiated
Reactor Fuel |
| NUREG-0737 |
Clarification of TMI Action Plan Requirements |
| NUREG-0750 |
Nuclear Regulatory Commission Issuances, Hardbound
Editions |
| NUREG-0800 |
Standard Review Plan for the Review of Safety Analysis
Reports for Nuclear Power Plants |
| NUREG-0847 |
Safety Evaluation Report
Related to the operation of
Watts Bar Nuclear Plant,
Units 1 and 2 |
| NUREG-0933 |
Resolution of Generic Safety Issues |
| NUREG-0936 |
NRC Regulatory Agenda: Semiannual Report |
| NUREG-0980 |
Nuclear Regulatory Legislation: 109th Congress |
| NUREG-1021 |
Operator Licensing Examination Standards for Power
Reactors |
| NUREG-1022 |
Event Reporting Guidelines 10 CFR 50.72 and 50.73 |
| NUREG-1055 |
Improving Quality and the Assurance of Quality in the Design and Construction of Nuclear Power Plants |
| NUREG-1065 |
Acceptable Standard Format and Content for the Fundamental
Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium
Facilities |
| NUREG-1100 |
Performance Budget |
| NUREG-1122 |
Knowledge and Abilities Catalog for Nuclear
Power Plant Operators: Pressurized Water Reactors |
| NUREG-1123 |
Knowledge and Abilities Catalog for Nuclear Power Plant
Operators: Boiling Water Reactors |
| NUREG-1150 |
Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants |
| NUREG-1220 |
Training Review Criteria and Procedures |
| NUREG-1262 |
Answers to Questions at Public Meetings Regarding Implementation
of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses |
| NUREG-1280 |
Standard Format and Content Acceptance Criteria for
the Material Control and Accounting (MC&A) Reform Amendment |
| NUREG-1307 |
Report on Waste Burial Charges |
| NUREG-1350 |
Information Digest |
| NUREG-1415 |
Office of the Inspector General Semiannual Report to
Congress |
| NUREG-1430 |
Standard Technical Specifications Babcock and Wilcox
Plants |
| NUREG-1431 |
Standard Technical Specifications Westinghouse Plants |
| NUREG-1432 |
Standard Technical Specifications Combustion Engineering
Plants |
| NUREG-1433 |
Standard Technical Specifications General Electric
Plants, BWR/4 |
| NUREG-1434 |
Standard Technical Specifications General Electric
Plants, BWR/6 |
| NUREG-1437 |
Generic Environmental Impact Statement for License
Renewal of Nuclear Plants |
| NUREG-1449 |
Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States |
| NUREG-1465 |
Accident Source Terms for Light-Water Nuclear Power Plants - Final Report |
| NUREG-1478 |
Operator Licensing Examiner Standards for Research and Test Reactors |
| NUREG-1501 |
Background as a Residual Radioactivity Criterion for Decommissioning |
| NUREG-1505 |
A Nonparametric Statistical
Methodology for the Design
and Analysis of Final Status
Decommissioning Surveys |
| NUREG-1513 |
Integrated Safety Analysis Guidance Document |
| NUREG-1501 |
Background as a Residual Radioactivity Criterion for Decommissioning |
| NUREG-1516 |
Management of Radioactive Material Safety Programs at Medical Facilities |
| NUREG-1520 |
Standard Review Plan for the Review of a License Application
for a Fuel Cycle Facility |
| NUREG-1536 |
Standard Review Plan for Dry Cask Storage Systems |
| NUREG-1542 |
NRC's Performance and Accountability Report |
| NUREG-1552 |
Fire Barrier Penetration Seals in Nuclear Power Plants |
| NUREG-1555 |
Standard Review Plans for Environmental Reviews for
Nuclear Power Plants |
| NUREG-1556 |
Consolidated Guidance About Materials Licenses |
| NUREG-1563 |
Branch Technical Position on the Use of Expert Elicitation
in the High-Level Radioactive Waste Program |
| NUREG-1567 |
Standard Review Plan for Spent Fuel Dry Storage Facilities |
| NUREG-1569 |
Standard Review Plan for In Situ Leach Uranium Extraction
License Applications |
| NUREG-1574 |
Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforcement |
| NUREG-1575 |
Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) |
| NUREG-1576 |
Multi-Agency Radiological Laboratory Analytical Protocols Manual |
| NUREG-1577 |
Standard Review Plan on Power Reactor Licensee Financial
Qualifications and Decommissioning Funding Assurance |
| NUREG-1609 |
Standard Review Plan for Transportation Packages for Radioactive Material |
| NUREG-1614 |
Strategic Plan |
| NUREG-1617 |
Standard Review Plan for Transportation Packages for Spent Nuclear Fuel |
| 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 |
| NUREG-1628 |
Staff Responses to Frequently Asked Questions Concerning
Decommissioning of Nuclear Power Reactors |
| NUREG-1635 |
Review and Evaluation of the Nuclear Regulatory Commission
Safety Research Program |
| NUREG-1640 |
Radiological Assessments for Clearance of Equipment
and Materials from Nuclear Facilities |
| NUREG-1649 |
Reactor Oversight Process |
| NUREG-1650 |
United States National Report for the Convention on
Nuclear Safety |
| NUREG-1700 |
Standard Review Plan for Evaluating Nuclear Power Reactor
License Termination Plans |
| NUREG-1703 |
Characterization of Radioactive Slags |
| NUREG-1705 |
Safety Evaluation Report Related to the License Renewal
of Calvert Cliffs Nuclear Power Plant, Units 1 and 2 |
| NUREG-1713 |
Standard Review Plan for Decommissioning Cost Estimates
for Nuclear Power Reactors |
| NUREG-1714 |
Final Environmental 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 |
| NUREG-1717 |
Systematic Radiological Assessment of Exemptions for
Source and Byproduct Materials |
| NUREG-1718 |
Standard Review Plan for the Review of an Application
for a Mixed Oxide (MOX) Fuel Fabrication Facility |
| NUREG-1720 |
Re-Evaluation of the Indoor Resuspension Factor for
the Screening Analysis of the Building Occupancy Scenario for NRC’s
License Termination Rule |
| NUREG-1723 |
Safety Evaluation Report Related to the License Renewal
of Oconee Nuclear Station, Units 1, 2 and 3 |
| NUREG-1725 |
Human Interaction with Reused Soil: An Information
Search |
| NUREG-1736 |
Consolidated Guidance: 10 CFR Part 20 - Standards for
Protection Against Radiation |
| NUREG-1739 |
Analysis of Public Comments on the Improved License
Renewal Guidance Documents |
| NUREG-1743 |
Safety Evaluation Report Related to the License Renewal
of Arkansas Nuclear One, Unit 1 |
| NUREG-1748 |
Environmental Review Guidance for Licensing Actions
Associated with NMSS Programs |
| NUREG-1757 |
Consolidated Decommissioning Guidance |
| NUREG-1758 |
Evaluation of Fire Models for Nuclear Power Plant Applications:
Cable Tray Fires |
| NUREG-1759 |
Safety Evaluation Report Related to the License Renewal
of Turkey Point Nuclear Plant, Units 3 and 4 |
| NUREG-1761 |
Radiological Surveys for Controlling Release of Solid
Materials |
| NUREG-1762 |
Integrated Issue Resolution Status Report |
| NUREG-1764 |
Guidance for the Review of Changes to Human Actions |
| NUREG-1765 |
Basis Document for Large Early Release Frequency (LERF) Significance Determination Process (SDP) Inspection Findings that May Affect LERF |
| 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 |
| NUREG-1767 |
Environmental Impact Statement on the Construction
and Operation of a Mixed Oxide Fuel Fabrication Facility at the Savannah
River Site, South Carolina |
| NUREG-1768 |
USNRC Package Performance Study Test Protocols |
| NUREG-1769 |
Safety Evaluation Report Related to the License Renewal
of Peach Bottom Atomic Power Station, Units 2 and 3 |
| NUREG-1772 |
Safety Evaluation Report Related to the License Renewal
of McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear
Station, Units 1 and 2 |
| NUREG-1773 |
Environmental Impact Statement for the Proposed Idaho
Spent Fuel Facility at the Idaho National Engineering and Environmental
Laboratory in Butte County, Idaho |
| NUREG-1774 |
A Survey of Crane Operating Experience at U.S. Nuclear
Power Plants from 1968 through 2002 |
| NUREG-1775 |
ISCORS Assessment of Radioactivity in Sewage Sludge:
Radiological Survey Results and Analysis |
| NUREG-1776 |
Regulatory Effectiveness of the Station Blackout Rule |
| NUREG-1777 |
Regulatory Effectiveness Assessment of Option B of
Appendix J |
| NUREG-1778 |
Knowledge Base for Post-Fire Safe-Shutdown Analysis |
| NUREG-1779 |
Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2 |
| NUREG-1780 |
Regulatory Effectiveness of the Anticipated Transient
Without Scram Rule |
| NUREG-1781 |
CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum
Mixing During a PWR Severe Accident |
| NUREG-1782 |
Safety Evaluation Report Related to the License Renewal
of the Fort Calhoun Station, Unit 1 |
| NUREG-1783 |
ISCORS Assessment of Radioactivity in Sewage Sludge: Modeling to Assess Radiation Doses |
| NUREG-1784 |
Operating Experience Assessment - Effects of Grid Events
on Nuclear Power Plant Performance |
| NUREG-1785 |
Safety Evaluation Report Related to the License Renewal
of H. B. Robinson Steam Electric Plant, Unit 2 |
| NUREG-1786 |
Safety Evaluation Report Related to the License Renewal
of R. E. Ginna Nuclear Power Plant |
| NUREG-1787 |
Safety Evaluation Report Related to the License Renewal
of the Virgil C. Summer Nuclear Station |
| NUREG-1788 |
CFD Analysis of Full-Scale Steam Generator Inlet Plenum
Mixing During a PWR Severe Accident |
| NUREG-1789 |
10 CFR Part 52 Construction Inspection Program Framework
Document |
| NUREG-1790 |
Environmental Impact Statement for the Proposed
National Enrichment Facility in Lea County, New Mexico - Final
Report |
| NUREG-1791 |
Guidance for Assessing Exemption Requests from
the Nuclear Power Plant Licensed Operator Staffing Requirements
Specified in 10 CFR 50.54(m) - Final Report |
| NUREG-1792 |
Good Practices for Implementing Human Reliability Analysis
(HRA) |
| NUREG-1793 |
Final Safety Evaluation Report Related to Certification
of the AP1000 Standard Design |
| NUREG-1795 |
FAVOR Code Versions 2.4 and 3.1 Verification and Validation
Summary Report |
| NUREG-1796 |
Safety Evaluation Report Related to the License Renewal
of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities
Nuclear Power Station, Units 1 and 2 |
| NUREG-1800 |
Standard Review Plan for Review of License Renewal
Applications for Nuclear Power Plants |
| NUREG-1801 |
Generic Aging Lessons Learned (GALL) Report |
| NUREG-1803 |
Safety Evaluation Report Related to the License Renewal
of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 |
| NUREG-1804 |
Yucca Mountain Review Plan |
| NUREG-1805 |
Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis
Methods for the U.S. Nuclear Regulatory Commission Fire Protection
Inspection Program |
| NUREG-1806 |
Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61) |
| NUREG-1807 |
Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1 |
| NUREG-1811 |
Environmental Impact Statement for an Early Site Permit (ESP) at the North Anna ESP Site |
| NUREG-1814 |
Status of the Decommissioning Program - 2006 Annual Report |
| NUREG-1815 |
Environmental Impact Statement for an Early Site Permit (ESP) at
the Exelon ESP Site |
| NUREG-1816 |
Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Plants |
| NUREG-1817 |
Environmental Impact Statement for an Early Site Permit (ESP) at
the Grand Gulf ESP Site |
| NUREG-1821 |
Final Safety Evaluation Report on the Construction Authorization Request for the Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina |
| NUREG-1823 |
U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials |
| NUREG-1824 |
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications |
| NUREG-1825 |
Safety Evaluation Report Related to the License Renewal of the Joseph M. Farley Nuclear Plant, Units 1 and 2 |
| NUREG-1826 |
APEX-AP1000 Confirmatory Testing To Support AP1000 Design Certification (Non-Proprietary) |
| NUREG-1827 |
Safety Evaluation Report for the National Enrichment Facility in Lea County, New Mexico, Louisiana Energy Services |
| NUREG-1828 |
Safety Evaluation Report Related to the License Renewal of the
Arkansas Nuclear One, Unit 2 |
| NUREG-1829 |
Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through
the Elicitation Process |
| NUREG-1830 |
Office of Investigations Annual Report |
| NUREG-1831 |
Safety Evaluation Report Related to the License Renewal of the
Donald C. Cook Nuclear Plant, Units 1 and 2 |
| NUREG-1832 |
Analysis of Public Comments on the Revised License Renewal Guidance Documents |
| NUREG-1833 |
Technical Bases for Revision to the License Renewal Guidance Documents |
| NUREG-1834 |
Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon, Ohio |
| NUREG-1835 |
Safety Evaluation Report for an Early Site Permit (ESP) at the
North Anna ESP Site |
| NUREG-1836 |
Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Approval of the License Termination Plan |
| NUREG-1837 |
Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14 |
| NUREG-1838 |
Safety Evaluation Report Related to the License Renewal of the Millstone Power Station,
Units 2 and 3 |
| NUREG-1839 |
Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 and 2 |
| NUREG-1840 |
Safety Evaluation of Early Site Permit Application in the Matter of System Energy Resources, Inc., a Subsidiary of Entergy Corporation, for the Grand Gulf Early Site Permit Site |
| NUREG-1842 |
Evaluation of Human Reliability Analysis Methods Against Good Practices |
| NUREG-1843 |
Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2, and 3 |
| NUREG-1844 |
Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC (EGC) ESP Site |
| NUREG-1850 |
Frequently Asked Questions on
License Renewal of Nuclear Power Reactors |
| NUREG-1851 |
Safety Evaluation Report for the American Centrifuge Plant in Piketon, Ohio |
| NUREG-1852 |
Demonstrating the Feasibility
and Reliability
of Operator Manual Actions in Response to Fire |
| NUREG-1853 |
History and Framework of Commercial Low-Level Radioactive Waste Management in the United States |
| NUREG-1854 |
NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations, Draft Final Report for Interim Use |
| NUREG-1855 |
Guidance on the Treatment
of Uncertainties
Associated with PRAs in
Risk-Informed Decision
Making (NUREG-1855) - Draft Report For Comment |
| NUREG-1856 |
Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2 |
| NUREG-1860 |
Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing, Volumes 1 and 2 |
| NUREG-1861 |
Peer Review of GSI-191 Chemical Effects Research Program |
| NUREG-1862 |
Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Generic Safety Issue 191 |
| NUREG-1863 |
Review of Responses to NRC Bulletin 2003-02-Leakage from Reactor Pressure Vessel Lower
Head Penetrations and Reactor Coolant Pressure Boundary Integrity |
| NUREG-1864 |
A Pilot Probabilistic Risk Assessment Of a Dry Cask Storage System At a Nuclear Power Plant |
| NUREG-1865 |
Safety Evaluation Report
Related to the License Renewal of
the Monticello Nuclear
Generating Plant |
| NUREG-1871 |
Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant |
| NUREG-1872 |
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site |
| NUREG-1873 |
Environmental Impact Statement for License Renewal Of the National Bureau of Standards Reactor |
| NUREG-1875 |
Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station |
| NUREG-1880 |
ATHEANA User’s Guide |
| NUREG-1885 |
Report to Congress on the
Security Inspection Program for
Commercial Power Reactor and
Category I Fuel Cycle Facilities:
Results and Status Update - Annual Reports |
| NUREG-1886 |
Joint Canada – United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages (NUREG-1886) - Draft Report for Comment |
| NUREG-1887 |
RASCAL 3.0.5: Description of
Models and Methods |
| NUREG-1888 |
Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma - Final Report |
| NUREG-1890 |
Evaluating Igneous
Activity at Yucca Mountain,
Technical Basis for
Decisionmaking |
| NUREG-1891 |
Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear
Power Station |
| NUREG-1900 |
Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 and 2 |
| NUREG-1903 |
Seismic Considerations For the Transition Break Size |
NUREG-1910
|
Generic Environmental
Impact Statement for
In-Situ Leach Uranium
Milling Facilities - Draft Report for Comment |
