PLA-4061, Forwards Summary Rept of Safety Evaluations Approved During Period from 920101-921231 for SSES Unit 1 & 2
LIC-13-0100, WCAP-17262-NP, Rev 1, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Fort Calhoun, Unit 1
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
LIC-11-0067, Response to Second NRC Request for Additional Information License Amendment Request to Relocate Operating & Surveillance Requirements for Power-Operated Relief Valve, Safety Valve Position, & Tail Pipe Temperature Instrumentation from Te
NRC-90-0017, Forwards Rev 3 to Radiological Emergency Response Plan, Incorporating Changes to Initiating Conditions for Notification of Unusual Event Emergency Classification
LIC-03-0160, Response to NRC RAI on Reactor Coolant System Leakage Limits Amendment Request
LIC-03-0050, License Amendment Request, Reactor Coolant System Leakage Limits
LIC-02-0034, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
LIC-94-0195, Monthly Operating Rept for Sept 1994 for Fort Calhoun Station
LIC-94-0133, Forwards Application for Amends to License DPR-40,revising Ts,To Incorporate Changes to Credit Leak Before Break Methodlogy to Resolve USI A-2, Asymmetrical Blowdown Loads on Rpcs
W3P90-1513, Forwards Supplemental Info for Rev 6,Change 1 to Inservice Testing Program Re Pumps & Valves.Info Revises Relief Requests 2.1.4,2.1.5 & 3.1.56.Relief Request 2.1.4 Has Been Withdrawn
L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006
05000285/LER-1988-005, :on 880309,discovered Condition in Which Specific LOCA Could Incapacitate Instrumentation Feeding Protective Function,Resulting in Loss of Pressurizer Pressure Transmitters Following Spray Break
05000285/LER-1990-028, :on 901214,investigation of Unknown RCS Leakage Identified Source as Installed Spare Control Element Drive Mechanism Housing 9.Caused by Lack of Venting Which Caused Igscc.Blank Flanges Installed
LIC-93-0074, Forwards Application for Amend to License DPR-40,changing TS 2.1.4 & TS Table 3-3 to Allow Closure of USI A-2, Asymmmetric Blowdown Loads on Reactor Primary Coolant Sys Per GL 84-04,by Implementing Changes to LBB Methodology
BECO-90-101, Application for Amend to License DPR-35,changing Tech Specs by Removing cycle-specific Parameter Limits & Relocating to Core Operating Limits Rept
3F0405-04, Transmittal of 2004 Radioactive Effluent Release Report
LIC-06-0002, License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a Generator Tube Repair
LIC-06-0087, Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a SGT Repair Method