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Issue date | Title | Topic | |
---|---|---|---|
ML20067C290 | 31 January 1991 | Proposed Tech Specs,Expanding Testing Tolerence of 480 Volt Molded Case Circuit Breakers | |
ML20069A476 | 13 May 1994 | Proposed Tech Specs Revises Surveillance Requirement 4.8.1.1.2e.8,which Requires That Diesel Generator Be Retested | |
ML20069H251 | 6 June 1994 | Proposed Tech Specs Removing Controls for Remote Shutdowm Sys Control Valve & Deleting Isolation Signal for Certain Primary Containment Isolation Valves as Result of Eliminating Steam Condensing Mode of RHR Sys | |
ML20069K028 | 9 June 1994 | Revised TS Pages Supporting TS Change Request 92-03-0 | Squib |
ML20069L582 | 10 June 1994 | Proposed Tech Specs Change Request 94-04-1,re one-time Change Affecting AOT for Esws;Rhrsw;Spc,Sp Spray,Lpci Modes of Rhrs;Cp Spray Sys to Be Extended from 3 & 7 to 14 Days During Third Refueling Outage Scheduled to Begin Jan 1995 | |
ML20069N859 | 15 June 1994 | Proposed TS Page 3/4 6-14,reflecting 24 Month Changes | |
ML20070F524 | 13 July 1994 | Proposed Tech Spec Bases Accurately Reflecting Safety Analysis Assumptions for Automatic Depressurization Sys | Fuel cladding |
ML20070J592 | 20 July 1994 | Proposed Tech Specs Raising Steam Leakage Detection Sys set-points That Isolate HPCI Sys & RCIC Sys Equipment on Equipment Room High Temp & High Delta Temp | Reactor Vessel Water Level |
ML20070J625 | 20 July 1994 | Proposed Tech Specs,Relocating Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & TS Bases to Updated FSAR | Reactor Vessel Water Level |
ML20070K273 | 20 July 1994 | Proposed Tech Specs Change Request 93-21-0,involving Retesting of Diesel Generator within 5 Min After Completing 24 H Endurance Run | |
ML20070L689 | 12 March 1991 | Proposed Tech Spec Sections 2.1.2,3.2.1 & 3.2.3 Re MCPR Safety Limit/Revised Calculational Methods | Fuel cladding |
ML20070N562 | 29 April 1994 | Proposed Tech Specs Revising Surveillance Intervals to Facilitate Change in Refueling Cycles from 18 to 24 Months | Reactor Vessel Water Level Scram Discharge Volume |
ML20071F428 | 16 May 1983 | Procedure HPA-63d, Calibr of Ventilation Sys Radiation Monitors | |
ML20071F446 | 16 May 1983 | Procedure HPA-77, Determination of Max Permissible Concentration Hours | |
ML20071F839 | 30 June 1994 | Proposed Tech Specs Re Relocating Selected Recirculation & Control Rod Block Instrumentation Setpoints | Shutdown Margin Scram Discharge Volume |
ML20071J540 | 22 July 1994 | Proposed Tech Specs,Reflecting Removal of Surveillance Frequency Details Governing 10CFR50,App J 'B' & 'C' Type Testing | Hydrostatic |
ML20072B880 | 4 August 1994 | Proposed Tech Specs & Associated Bases Re Toxic Gas Detection Sys | Fire Protection Program Fire Watch |
ML20072B922 | 4 August 1994 | Proposed Tech Specs,Revising Requirements for Holding SRO Licenses for Certain Plant Mgt Positions to Require Only Superintendent - Operations or Assistant Superintendent - Operations to Hold SRO License | |
ML20072D248 | 12 August 1994 | Proposed TS Section 3.5.1,Action C, Including New Action Statement in Event That HPCI Sys & One CS Subsystem & or One LPCI Subsystem Inoperable | Safe Shutdown Fuel cladding |
ML20072K005 | 22 August 1994 | Proposed Tech Specs Re CR Block Instrumentation,Standby Liquid Control Sys Operability in Mod 5,scram Discharge Volume Valve Testing,Optional Method of Scram Testing & Defination of Core Alteration | Shutdown Margin Packing leak Scram Discharge Volume Fuel cladding |
ML20072Q939 | 23 August 1994 | Proposed Tech Specs,Reflecting Removal of 125/130 Volt Dc Class 1E Baatery Load Cycle Table | |
ML20072Q958 | 31 August 1994 | Proposed Tech Specs,Relocating Turbine Overspeed Protection Sys Requirements,Relocating Primary Containment Conductor Protection Device Requirements & Revising Fw/Main Turbine Trip Sys Actuation Requirements | Shutdown Margin Hydrostatic Fire Watch |
ML20073C791 | 16 September 1994 | Proposed Tech Specs,Revising TS SR 4.7.4.e & Associated Bases Section 3/4.7.4 to Extend Snubber Functional Testing Interval from 18 Months to 24 Months to Increase Sample Plan Size | High Radiation Area |
ML20073H937 | 30 April 1991 | Proposed Tech Specs Incorporating Generic Ltr 90-09 | |
ML20073S779 | 30 June 1994 | Proposed TS Tables 3.3.7.4-1 & 3.6.3-1 Re Certain Remote Shutdown Sys Control Valves & Primary Isolation Valves | |
ML20073S947 | 21 June 1994 | Non-proprietary Revised Emergency Response Procedures, Including Revs 43 & 44 to Index,Rev 10 to ERP-300 & Rev 9 to & ERP-500 | Safe Shutdown |
ML20074B081 | 16 May 1983 | Procedure HPO/CO-3, Airborne Activity Survey Techniques, Including Techniques for Constant Air Monitors,Portable Fixed Filter Samplers & Charcoal Cartridges | |
ML20074B084 | 16 May 1983 | Procedure HPO/CO-65, Field Use of Low Vol Portable Air Sampler | |
ML20076K658 | 25 October 1994 | Proposed Tech Specs Re Change Request to Increase Allowable Leak Rate for MSIV & Delete MSIV LCS | |
ML20077D566 | 2 December 1994 | Proposed Tech Specs Re Relocation of Fire Protection Requirements,Per GLs 86-10 & 88-12 | Safe Shutdown Reactor Vessel Water Level Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20077M381 | 31 August 1983 | Detailed Control Room Design Review Program Plan for Limerick & Peach Bottom Plants | |
ML20077N051 | 27 June 1983 | Static Load Test Program on 18-Inch Butterfly Valve Assembly W/Limitorque Operator | |
ML20077N071 | 1 September 1983 | Nuclear Qualification Test Rept | |
ML20077N081 | 1 September 1983 | Summary of Generic Qualification of Solenoid Valves | |
ML20077N090 | 28 August 1980 | Rev 1 to Qualification of EA180 Series Limit Switches for Use in Nuclear Power Plants in Compliance W/Ieee Stds 323-1974,382-1972 & 344-1975 | Boric Acid Safe Shutdown Earthquake Thermoset Earthquake |
ML20077N096 | 24 June 1982 | Hydrodynamic Vibration Testing (New Loads) | |
ML20078K279 | 27 January 1995 | Proposed Tech Specs,Eliminating TS Active Safety Function Designation of Eight Drywell Chilled Water Sys Valves | Stroke time Hydrostatic |
ML20078L303 | 21 November 1994 | Proposed Tech Specs Re Administrative Section 6.0 | Safe Shutdown High Radiation Area Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
ML20078L626 | 22 November 1994 | Proposed Tech Specs Re Increased Spent Fuel Pool Storage Capacity of Each Unit | |
ML20078N247 | 7 February 1995 | Proposed Tech Specs Page 3/4 6-2 Re MSIV Leakage Control Sys | |
ML20078R744 | 3 October 1983 | Rev 1 to Methodology for Evaluation of Fire Resistance of Structural Steel | |
ML20079A327 | 22 February 1995 | Proposed Tech Specs to Revise Listed TS SRs to Clarify EDG Acceptable Steady State Voltage Range | |
ML20079J942 | 31 December 1983 | Rev 0 to Offsite Dose Calculation Manual | Offsite Dose Calculation Manual |
ML20080M381 | 19 August 1983 | Rev 0 to Procedure 8031-G-14, General Project Requirements for Seismic Design & Analysis of Equipment Supports | |
ML20080M382 | 2 August 1981 | Rev 1 to Procedure 8031-G-19, Required Response Spectra (RRS) of Primary Containment for Load Combinations of Seismic & Hydrodynamic Loads | Safe Shutdown Earthquake Operating Basis Earthquake |
ML20080M384 | 29 January 1982 | Rev 2 to Procedure 8031-G-19, Required Response Spectra (RRS) of Reactor Bldg & Control Room Structure for Load Combinations of Seismic & Hydrodynamic Loads | Safe Shutdown Earthquake Operating Basis Earthquake |
ML20080N117 | 30 April 1994 | Rev 12 to LGS Units 1 & 2 Odcm | Loop seal Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20080N129 | 6 June 1994 | Rev 13 to LGS Units 1 & 2 Odcm | |
ML20080N140 | 9 June 1994 | Rev 14 to LGS Units 1 & 2 Odcm | Loop seal Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20080N146 | 31 December 1994 | Rev 15 to LGS Units 1 & 2 Odcm |