RIS 2004-09, Status on Deferral of Active Regulation of Ground-Water Protection at in Situ Leach Uranium Extraction Facilities
RIS 2008-06, Protection Against the Malevolent Use of Vehicles When Utilizing Landform Obstacles
RIS 2002-15, OMB Control No.: 3150-0002 NRC Regulatory Issue Summary 2002-15 NRC Approval of Commercial Data Encryption Systems for the Electronic Transmission of Safeguards Information
RIS 2006-14, NRC Regulatory Issue Summary - Enforcement Requirements for Facility Changes Under 10 CFR 70.72 (C) (2)
Information Notice 2008-10, Response to Indications of Potential Tampering, Vandalism, or Malicious Mischief
Information Notice 2008-14, Criticality Safety-related Events Resulting from Fissile Material Operations Under Procedures Not Reviewed by Criticality Safety Staff
Information Notice 2007-32, Out of Service Equipment Connected to in Service Process Line Results in Fissile Solution Spill at Fuel Cycle Facility
Information Notice 2007-30, Radiological Controls Create Criticality Safety Accident Scenario for Fissile Solution Container Transport at Fuel Cycle Facility
RIS 2008-03, Return/Reuse of Water Containing Previously Discharged Radioactive Effluents from Operating Nuclear Power Plants
Information Notice 2007-23, Inadvertent Discharge of Halon 1301 Fire Suppression System Due to Incorrect And/Or Out of Date Procedures
Information Notice 2007-22, Recent Hydrogen Fluoride Exposures at Fuel Cycle Facilities
Information Notice 2007-20, Use of Blank Ammunition
Information Notice 2006-10, Use of Concentration Control for Criticality Safety
Information Notice 2006-07, Inappropriate Use of a Single Parameter Limit as a Nuclear Criticality Safety Limit at Fuel Cycle Facilities
Information Notice 2006-02, Use of Galvanized Supports and Cable Trays with Meggitt Si 2400 Stainless Steel Jacketed Electrical Cables
Information Notice 2005-28, Inadequate Test Procedure Fails to Detect Inoperable Criticality Accident Alarm Horns
Information Notice 2005-22, Inadequate Criticality Safety Analysis of Ventilation Systems at Fuel Cycle Facilities
Information Notice 2005-13, Potential Non-Conservative Error in Modeling Geometric Regions in the Keno-V. a Criticality Code
Information Notice 2005-12, Excessively Large Criticality Safety Limits Fail to Provide Double Contingency at Fuel Cycle Facility
Information Notice 2005-05, Improving Material Control and Accountability Interface with Criticality Safety Activities at Fuel Cycle Facilities
Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions in Criticality Safety Analysis at Fuel Cycle Facilities
RIS 2004-02, Deferral of Active Regulation of Ground-Water Protection at in Situ Leach Uranium Extraction Facilities
Information Notice 2002-31, Potentially Defective UF6 Cylinder Valves (1-inch)
Information Notice 2002-24, Potential Problems with Heat Collectors on Fire Protection Sprinklers
Information Notice 2007-19, Fire Protection Equipment Recalls and Counterfeit Notices
Information Notice 2005-32, Product Alert for Fire Hydrants
Information Notice 2005-31, Potential Non-Conservative Error in Preparing Problem-Dependant Cross Sections for the Keno V. a or KENO-VI Criticality Code
RIS 2005-28, Scope of For-Cause Fitness-For-Duty Testing Required by 10 CFR 26.24(a)(3)
RIS 2005-22, Transportation Security Requirements for Special Nuclear Material of Moderate and Low Strategic Significance, 10 CFR Part 73 Vs. Regulatory Guide 5.59 (1983)
Information Notice 2003-10, Criticality Monitoring System Degradation at Bwx Technologies, Inc., Nuclear Products Division Lynchburg, VA
RIS 2002-12F, Category III Fuel Facilities NRC Threat Advisory & Protective Measures System
RIS 2002-07, Subject, Clarification of NRC Requirements Applicable to Worker Fatigue and Self-Declarations of Fitness-For-Duty
LD-92-099, Advises That Vendor in Process of Developing Tier 1 Design Descriptions & Accompanying ITAAC for Sys 80+.Proposes Delay in Submittal of ITAAC Submittal Until Package Can Accomodate Guidance from 920826 Meeting in San Jose,Ca
LD-92-075, Advises That Tier 1 Design Info & Insps,Tests,Analyses & Acceptance Criteria Submittal for Sys 80+ Will Be Provided by 921016
LD-92-089, Forward Draft Rev of Pilot ITAAC for Sys 80+ Std Design,In Response to NRC 920521 Comments on 920430 Submittal.Revs Account for Comments Provided by NUMARC & Reflect Comments Obtained in NUMARC 920716 Meeting
L-98-007, Requests to Meet W/Nrc at Earliest Convenience to Discuss Methods Being Used to Conduct Isa.Licensee Believes It Prudent to Delay ISA Methods Submittal Pending Discussions at Meeting
L-98-003, Provides Corrected Page Re Avlis Quality Assurance Program Description,Encl w/980303 Ltr
RA96-510, Application for Amend to License SNM-33,increasing Possession Limit in Order to Eliminate Undue Burden Re Managing SNM Inventory
L-96-505, Responds to NRC Request in Ltr Re Amend Request from Combustion Engineering to Downgrade License SNM-1067,
L-96-504, Requests Extension to Interim Storage Period by Increasing Time from 5 Yrs to 10 Yrs
L-96-503, Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 14
L-93-045, Provides Revised Organization Chart for License SNM-1067 W/Description for Each Key Position to Safety
L-93-062, Requests Extension on Completion Date for Next Assessment from 940117 to 0315 Re Fundamental Nuclear Matl Control Plan Due to Extraordinary Workloads of Qualified Independent Individuals Intended to Perform Assessment
L-93-061, Revised Application for Amend to License SNM-1067,expanding Residue Enrichment Limit to Include SNM Below 20 W/O U-235
L-93-056, Addendum to 931021 Applicaton for Amend to License SNM-1067, Allowing Use of Fire Hoses in Bldg 17
L-93-039, Confirms Termination of Nuclear Fuel Mfg Activities at Facility,Per Commitment Made in
L-93-106, Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued
L-98-006, Summarizes Progress on pre-application Activities Since USECs & Provides Response to NRC 980327 Request for Avlis Schedule Info