PLA-4061, Forwards Summary Rept of Safety Evaluations Approved During Period from 920101-921231 for SSES Unit 1 & 2
2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
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
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
TMI-11-075, Response to Request for Additional Information Related to Technical Specification Change Request No. 351 Maximum Allowable Power with Inoperable Main Steam Safety Valves
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
LR-N08-0205, Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
05000530/LER-1991-010-01, :on 911115,mobile Crane Came in Contact W/ Energized 13.8 Kv Power Line,Resulting in Deenergization of Offsite Power.Caused by Personnel Error.Crane Operating Engineer Site Access Revoked
05000528/LER-1988-010-01, :on 880706,ground Fault in 13.8 Kv Bus Caused Fire in Unit Auxiliary Transformer & Reactor Trip.Caused by Bullet Hole Point Faults in Phase Bus B Adjacent to Support Bar.Fire Extinguished & Bus Reenergized
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
L-2006-229, Response to Request for Additional Information - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
HNP-06-116, Response to Request for Additional Information Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
L-2006-094, Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.90
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
NOC-AE-05001921, License Amendment Request - Proposed Amendment to Technical Specifications to Incorporate Best Estimate Analyzer for Core Operations - Nuclear
L-05-063, Pressure and Temperature Limits Reports, Revision 1
W3F1-2002-0095, License Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
B12359, Application for Amend to License NPF-49,changing Tech Spec Sections 3.4.1.3 & 3/4.4.1 Re Limiting Condition for Operation for Number of Reactor Coolant Loops in Operation During Hot Shutdown Conditions.Fee Paid
ST-HL-AE-2320, Clarifies Control Rod Drop Testing,Per NRC Review of Util Initial Startup Testing Program.During Drop Testing at Hot - No Flow Conditions Not Required Due to Listed Reasons,Per Reg Guide 1.68.Clarification to FSAR Test Description Encl
2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)
B14108, Application for Amend to License NPF-49,changing TS Figure 3.1-5, Required Shutdown Margin for Mode 5 W/Rcs Loops Not Filled, Section 3.4.1.3, RCS - Hot Shutdown & 4.4.1.1.3, RCS - Hot Shutdown Surveillance Requirements
NRC-84-0080, Forwards Responses to 840507 Request for Addl Info Per Reactor Sys Branch Review of Tech Specs.Info Documents Certain Objections to Timeliness & Scope of Review
NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
L-04-074, License Amendment Request Nos. 326 and 177
L-2006-089, Proposed License Amendment Steam Generator Tube Integrity
L-2007-071, Reply to Request for Additional Information Re Steam Generator Tube Integrity Amendment Request
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000382/LER-1988-013, :on 880528,fire Protection Sprinkler Found Isolated After Restoration from Testing.Caused by Personnel Error.Procedures Being Revised to Require Contaminated Valve Lineup Sheets Be Photocopied or Verified
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000416/LER-1984-041, :on 840909,more than One Jet Pump Failed diffuser-to-lower-plenum Differential Pressure Surveillance Testing.Cause Not Stated.Three Transmitters Replaced & Three Recalibr
05000272/LER-1984-015-01, :on 840611,received Notification by Westinghouse of Potential Unreviewed Safety Question Re Consistency Between Safety Analysis & Tech Specs.Procedures for Mode 3 Operation Revised
05000416/LER-1993-008, :on 930913,reactor Scram Occurred Due to Actuation & Injection of HPCS Sys,As Result of HPCS Low Water Level Channels C & G Generating Erroneous Level Signal.No C/As Necessary for HPCS Actuation
HNP-12-130, Transmittal of Technical Specifications Bases
HNP-15-046, Transmittal of Technical Specifications Bases
2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000397/LER-1996-003, :on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures Revised
05000397/LER-1991-002, :on 910110,reactor Recirculation Sys Jet Pump Operability Surveillance Testing Did Not Meet Literal Compliance W/Tech Specs.Caused by Inadequate Procedure. Procedure Revised
GO2-91-039, Application for Amend to License NFP-21,revising Tech Spec 3.4.1.2, Jet Pumps
GO2-95-228, Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
TMI-11-077, Supplemental Response to Request for Additional Information Related to Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-02-094, Technical Specifications Bases Change Submittal
05000289/LER-2009-001, Regarding Multiple Main Steam Safety Valve Test Failures
05000251/LER-2005-005, Re Loss of Offsite Power Causes Engineered Safety Feature Actuations
B18921, License Basis Document Change Request 3-13-02 Elimination of N-1 Loop Operation from Technical Specifications - Response to Request for Additional Information
05000325/LER-1989-011, :on 890404,determined That Reactor Jet Pump Once Per 24 H Operability Surveillance Had Been Missed Prior to Entering Operation Condition 2.Caused by Inadequate Review of Surveillance Rept
RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
05000498/LER-2024-004-01, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps