3F1114-01, Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90
CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry
RS-09-113, Response to Request for Additional Information Regarding Relief Request CR-26
B17214, Provides NRC W/More Detailed Explanation of Changes,Decision Making Process & Performance Measures Util Will Use to Guide Transition
ST-HL-AE-1377, Forwards Responses to Reg Guide 9.3 Re Antitrust OL Review, Including Changes & Updates Which Occurred Since Sept 1980
ST-HL-AE-1823, Forwards Proprietary & Nonproprietary Suppl 1 to WCAP-11256 & WCAP-11257,respectively, Technical Bases for Eliminating Pressurizer Surge Line Ruptures..., Per NRC 861015 Request. W/O Proprietary Rept.Related Correspondence
3F0885-15, Semiannual Radioactive Effluent Release Rept,Jan- June 1985
05000277/LER-1981-028-01, /01T-0:on 810428,determined That More Detailed Analysis Was Required & Minor Mods Were Necessary to Assure That Certain Fans Would Perform During Earthquakes.Caused by Fan Supports Not Meeting Seismic Requirements
05000454/LER-1985-033, :on 850314,particulate Filter & Iodine Cartridge Collected from Auxiliary Bldg Vent Stack Monitors 1RE-PR028 & 2RE-PR028 Not Analyzed as Required by Tech Spec Table 4.11-2.Caused by Personnel Error
3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability
05000318/LER-1994-006-01, :on 941027,Unit 2 Tripped on Receipt of Reactor Protective Sys Loss of Load Signal.Caused by Failure to Adequately Address Potential Risks of Work Newly Assumed by Electrical Maint Group.New Links Installed
W3P89-2161, 1989 Rept of Facility Changes,Tests & Experiments Per 10CFR50.59
RBG-28318, Responds to NRC Bulletin 87-002,Suppls 1 & 2 Re Fastener Testing to Determine Conformance W/Applicable Matl Specs. Info Requested by Action Items 1 & 2 Encl
05000309/LER-1979-024-99, /99X-0:on 791017,reactor Coolant Dose Equivalent Iodine Exceeded Tech Spec Limits of 1.0 Uci/G.Caused by Unscheduled Plant Trip.Monitoring Program Established Following Trip to Adhere to Iodine Trends
L-81-153, Forwards Response to IE Bulletin 80-11, Masonry Wall Design. All Walls Have Been re-evaluated to Meet Intended Function Under Appropriate Loads & Load Combinations
L-84-333, Forwards Status of Resolution of License Conditions Covering Inservice Insp Program,Axial Growth & Fire Protection.Deletion of Completed Conditions in Future License Amend Requested
HCH-2014-025, Submittal of Discharge Monitoring Report for the Month of May 2014
LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual
L-12-276, Technical Specification 5.6.6 Steam Generator Tube Inspection Report