LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
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
L-06-119, Supplement to License Amendment Request Nos. 324 and 196, Steam Generator Tube Integrity
L-06-088, Supplement to License Amendment Request Nos. 324 & 196 Steam Generator Tube Integrity
LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen
B17413, Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA
BSEP-96-0123, Application for Amends to Licenses DPR-62 & DPR-71,revising TS to Allow Uprate of Facilities to 105% of Rated Thermal Power.Proprietary & Nonproprietary Versions of GE Power Uprate SAR for Bsep... Encl.Proprietary GE Rept Withheld
L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
L-2006-089, Proposed License Amendment Steam Generator Tube Integrity
B13032, Proposed Tech Specs Pages 3/4 4-7,3/4 4-9,B 3/4 4-2a & B 3/4 4-3 Re Surveillance Requirements for RCS Leakage
05000413/LER-1985-041, :on 850613,main Feedwater Pump Trip Resulted in Manual Reactor Trip.Caused by Pump Recirculation Valve Not Capable of Modulating Quickly During Flow Reduction.Design Deficiency Corrected
05000369/LER-1990-025, :on 900827,shutdown Because of Unidentified RCS Leakage Greater than TS Limits Occurred Due to Equipment Failure
05000498/LER-1990-017, :on 900706,determined That Personnel Failed to Adequately Perform Tech Spec Required Surveillance on Reactor Coolant Pressure Isolation Valves.Caused by Misinterpretation.Addl Training Provided
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000369/LER-1990-025-01, :on 900827,Unit 1 Shut Down Because of Unidentified RCS Leakage Exceeding Tech Spec Limits.Caused by Equipment Failure.Procedure AP/1/A/5500/10 Implemented. Valve 1NC-33 Will Be Repacked at Next Outage
GO2-94-005, Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements
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
L-05-144, License Amendment Request Nos. 324 and 196 Re Steam Generator Tube Integrity
LR-N05-0018, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational
L-95-169, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation