Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML19325D293 | 10 October 1989 | Proposed Tech Specs Change Request 89-11,revising Surveillance Requirement 4.7.4.b Initial Visual Insp of Snubbers. | |
| ML19327A891 | 11 October 1989 | Proposed Tech Specs Reducing Number of Suppression Chamber to Drywell Vacuum Breaker Pairs Required to Be Operable as Three | |
| ML19327B864 | 3 November 1989 | Proposed Tech Specs,Deleting Figures 6.2.1-1 & 6.2.2-1 Re Organization | Safe Shutdown Offsite Dose Calculation Manual Process Control Program |
| ML19327B942 | 3 November 1989 | Proposed Tech Specs Re Removal of Organizational Charts from Tech Specs as Recommended by Generic Ltr 88-06, Removal of Organization Charts from Tech Spec Administrative Control Requirements. | Safe Shutdown Process Control Program |
| ML20005E790 | 29 December 1989 | Proposed Tech Spec Section 3/4.4.6, Pressure/Temp Limits & Associated Bases | Hydrostatic |
| ML20006D936 | 29 January 1990 | Proposed Tech Specs,Allowing Source Range Monitor Count Rate to Be Reduced While Ensuring That Design Level of Counting Certainty Maintained.Ge Rept Withheld | Shutdown Margin Scram Discharge Volume |
| ML20011F657 | 23 February 1990 | Proposed Tech Specs Re Core Operating Limits Rept & cycle- Specific Parameter Limits | Shutdown Margin Abnormal operational transient Scram Discharge Volume Annual Radiological Environmental Operating Report Process Control Program Fuel cladding |
| ML20012E501 | 20 March 1990 | Proposed Tech Specs Making Administrative Changes to Eliminate Differences Between Units 1 & 2 Tech Specs | Safe Shutdown Reactor Vessel Water Level Annual Radiological Environmental Operating Report Pressure Boundary Leakage Offsite Circuit |
| ML20024D193 | 6 July 1978 | Revised Testing Procedure 10-T2, Multiple Channels, | |
| ML20028B424 | 1 September 1982 | Design Verification Test Rept,Internal Panel Control Wiring Separation Criteria. | Hot Short Safe Shutdown Thermoset |
| ML20029D447 | 27 April 1994 | Proposed Ts,Reflecting Deletion of SR 4.4.1.1.1 | |
| ML20043A366 | 16 May 1990 | Proposed Tech Specs Re Surveillance Requirements for Visual Insp of Snubbers | Grace period |
| ML20043D221 | 1 June 1990 | Proposed Tech Specs Change Request 90-05-1,deleting Ref to Water Temp at Suction of RHR Pump for Suppression Pool Water Temp Indication at Remote Shutdown Panel | Reactor Vessel Water Level |
| ML20043D855 | 29 May 1990 | Proposed Tech Specs Consisting of Change Request 89-07 Re Radiological Effluent Tech Specs | |
| ML20043H074 | 14 June 1990 | Proposed Tech Specs Re Replacement of 1,300 Hydraulic Control Unit Isolation Boundaries W/Four Newly Installed Isolation Boundaries on Common CRD Headers | Stroke time Hydrostatic |
| ML20044A113 | 22 June 1990 | Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Refueling Platform | |
| ML20044B120 | 11 July 1990 | Proposed Tech Spec Table 3.6.3-1 Re Primary Containment Isolation Valves | |
| ML20044B269 | 13 July 1990 | Proposed Tech Spec Section 6.0 Re station-qualified Reviewer Program | High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
| ML20044H192 | 26 April 1993 | Primary Reactor Containment Integrated Leakage Rate Test, Final Rept | |
| ML20046A401 | 16 July 1993 | Proposed Tech Specs Requesting TS to Allow Dual Role Sro/Sta Position | |
| ML20056D338 | 3 August 1993 | Proposed Tech Specs 3/4 3-80,3/4 6-29 & 3/4 6-30 Removing Control Sys Shutdown Sys Control Valves | |
| ML20056G098 | 28 December 1992 | Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS | Offsite Dose Calculation Manual Process Control Program |
| ML20056G492 | 27 August 1993 | Proposed Tech Specs Supporting Change in Calculated Peak Fuel Cladding Temp | Shutdown Margin Reactor Vessel Water Level Packing leak Offsite Dose Calculation Manual Abnormal operational transient Scram Discharge Volume Process Control Program Overtravel Fuel cladding Pressure Boundary Leakage |
| ML20056G495 | 25 August 1993 | Proposed TS Surveillance Requirement 4.5.1 to Reduce Frequency for Venting ECCS Piping from Every 31 Days to Every 6 Months | |
| ML20056G567 | 27 August 1993 | Proposed Tech Spec Change 93-14-2,extending AOT for RHR Svc Water Sys as Well as Suppression Pool Spray & Suppression Pool Cooling Modes of RHR Sys to 288 H | |
| ML20056G883 | 25 August 1993 | Proposed Tech Specs Section 3.3.7.8.2 & Associated Bases 3/4.3.7.8 to Modify Main Control Room Toxic Gas Detection Sys Alarm Logic | Reactor Vessel Water Level Fire Protection Program Fire Watch |
| ML20056H129 | 25 August 1993 | Proposed Tech Specs SR 4.7.1.3 Re Spray Pond | Ultimate heat sink |
| ML20058B371 | 19 October 1990 | Proposed Tech Specs Re RETS | |
| ML20058C572 | 17 November 1993 | Proposed TS Change 92-08-0,reflecting Operating Domain for Facility,Resulting from Proposed Implmentation of APRM-rod Block Monitor Ts/Max Extended Load Line Limit Analysis | |
| ML20058G891 | 30 November 1993 | Proposed Tech Specs SR 4.6.1.2.a,permitting Type a Test Presently Required to Be Performed During Fifth Unit 1 Refueling Outage,To Be Extended to Sixth Unit 1 Refueling Outage | |
| ML20058G911 | 30 November 1993 | Proposed Tech Specs SR 4.6.2.1.d,extending Surveillance Interval of Primary Containment drywell-to-suppression Chamber Bypass Leak Test from Current 18 Month Interval to 40 +/- 10 Month Interval | |
| ML20058L449 | 9 December 1993 | Proposed Tech Specs Supporting Planned Implementation of Power Rerate Program at Plant | Reactor Vessel Water Level Hydrostatic Scram Discharge Volume Fire Protection Program |
| ML20059E650 | 3 April 1990 | Rev 8 to Odcm | |
| ML20059G364 | 10 January 1994 | Proposed TS Sections 3.3.7.2 & 4.3.7.2,relocating Seismic Monitoring Instrumentation Lco,Srs & Associated Bases to Updated FSAR | Earthquake |
| ML20059G915 | 29 October 1993 | Proposed Tech Specs Re Main Steam Line Radiation Monitor Sys High Radiation Trip Function for Initiating Automatic Reactor Scram & Automatic Closure of Main Steam Line Isolation Valves | Reactor Vessel Water Level Scram Discharge Volume |
| ML20059K583 | 14 January 1994 | Proposed Tech Specs Increasing Allowable Leak Rate for MSIV & Deleting MSIV LCS | Design basis earthquake Earthquake |
| ML20059K594 | 14 January 1994 | Proposed Tech Specs 5.5.1.1, Criticality & 5.5.3, Capacity, Supporting Implementation of Mod to Install New High Density Spent Fuel Storage Racks in Each Spent Fuel Pools at LGS | |
| ML20062L599 | 20 December 1993 | Corrected Proposed TS Page 3/4 7-1 Re RHRSW | |
| ML20063D811 | 7 February 1980 | Erosion & Sedimentation Control Plan, Revision 3 | |
| ML20064D597 | 6 May 1982 | Pump & Valve Inservice Testing Program Plan, Rev 3 | |
| ML20065A867 | 24 March 1994 | Proposed Tech Specs Supporting Change in Frequency for Submitting Semiannual Effluent Release Rept to NRC from Semiannually to Annually | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program |
| ML20065E517 | 28 March 1994 | Proposed Tech Specs,Increasing Surveillance Interval for Reactor Protection Sys Electrical Power Monitoring Channels | |
| ML20065M673 | 26 November 1990 | Rev 19 to Limerick Generating Station Trip Bases Procedures Index | |
| ML20065N430 | 18 April 1994 | Proposed TS for Extension of Surveillance Intervals & AOTs for Containment Isolation Instrumentation & Other Selected Actuation Instrumentation,Incorporating Info from Recently Issued TS Amends & Correcting Typos | Shutdown Margin Fire Protection Program Fire Watch Failure to Scram |
| ML20065S115 | 6 December 1990 | Rev 2 to ON-120 Bases, Fuel Handling Problems | |
| ML20065S117 | 6 December 1990 | Procedures Index to Rev 2 to ON-120 Bases, Fuel Handling Problems | |
| ML20065S245 | 6 May 1994 | Proposed Tech Specs Permitting Interim Increase in Spent Fuel Storage Capacity in Unit 1 Spent Fuel Pool from 2040 Fuel Assemblies to 2500 Fuel Assemblies | |
| ML20065T495 | 21 December 1990 | Proposed Tech Spec Sections 4.0.5,3.4.3.2,4.4.3.2,per Generic Ltr 88-01 | Pressure Boundary Leakage |
| ML20066G525 | 30 November 1990 | Primary Reactor Containment Integrated Leakage Rate Test, Final Rept | |
| ML20067C281 | 31 January 1991 | Proposed Tech Specs,Eliminating Surveillance Requirement 4.9.2.b.1 | Shutdown Margin |