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Issue date | Title | Topic | |
---|---|---|---|
ML20207C287 | 11 November 1998 | Rev 5 to LACBWR Odcm | |
ML20207C280 | 11 November 1998 | Rev 7 to LACBWR Pcp | Annual Radioactive Effluent Release Report Process Control Program |
ML20141B774 | 9 May 1997 | Proposed Tech Specs,Changing LACBWR Controlling Documents | |
ML20059L627 | 5 November 1993 | Proposed Tech Specs Per Requirements of Revised 10CFR20 Regulations for Radiation Protection | |
ML20247G000 | 28 March 1989 | Proposed Tech Specs Re Controlled Area,Effluent Release Boundary,Exclusion Area,Frequency Notation,Fuel Handling & Process Control Program | Offsite Dose Calculation Manual Process Control Program |
ML20235G876 | 15 February 1989 | Proposed Tech Spec 5.4.2.2.a,reflecting Revised Proposed Min Inventory of 150 Gallons Per Fuel Storage Tank | |
ML20204H164 | 13 October 1988 | Proposed Tech Specs,Revising Radiological Environ Monitoring Program for Checking for Prescence of I-131 | |
ML20147B779 | 22 February 1988 | Proposed Tech Specs,Revising LACBWR Tech Specs | Unanalyzed Condition High Radiation Area Grab sample Offsite Dose Calculation Manual Hydrostatic Process Control Program Fire Protection Program Fire Watch Grace period |
ML20149N101 | 22 February 1988 | Revised Tech Specs Pages for 870930 Application for Amend to License DPR-45 | Ultimate heat sink |
ML20149D714 | 29 January 1988 | Proposed Tech Specs Changing Sentence in Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor | |
ML20236Q644 | 12 November 1987 | Proposed Tech Specs,Revising Administrative Section Due to Permanent Shutdown of Plant on 870430 | |
ML20235V685 | 30 September 1987 | Proposed Tech Specs Eliminating Sections That Do Not Apply as Result of Plant Shutdown on 870430 | Shutdown Margin Reactor Vessel Water Level Packing leak Fuel cladding Pressure Boundary Leakage |
ML20237F780 | 21 August 1987 | Proposed Tech Specs,Deleting Requirements Re Type a Leak Rate Tests | |
ML20237J303 | 18 August 1987 | Proposed Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 Reflecting Permanent Shutdown | |
ML20205P831 | 24 March 1987 | Proposed Tech Specs Figures 6.2.1-1,6.2.2-1 & Page 6-8, Revising Facility Organization | |
ML20207J816 | 19 December 1986 | Proposed Tech Specs Re Nuclear Instrumentation,Reflecting Replacement of Aging Equipment & Provision of Shutdown Functions for Reactor W/Numac Instruments from GE | Hot Short Abnormal operational transient |
ML20212B364 | 17 December 1986 | Proposed Tech Specs Altering Requirements for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 | |
ML20205M583 | 7 April 1986 | Proposed Tech Specs Reflecting Reorganization of Offsite Mgt Staff | |
ML20203B283 | 7 April 1986 | Proposed Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits | |
ML20202A915 | 1 April 1986 | Proposed Tech Specs Changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate | Reactor Vessel Water Level |
ML20153G132 | 21 February 1986 | Proposed Tech Specs,Clarifying & Correcting Description of Electrical Power Sys | |
ML20210B870 | 4 February 1986 | Proposed Changes to Tech Spec Sections 4.2.3 & 2.6, Describing Replacement & Mod of Noninterruptible Bus 1C | Backfit |
ML20138J775 | 12 December 1985 | Proposed Tech Specs,Incorporating Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10 | Power change |
ML20138J898 | 12 December 1985 | Proposed Tech Specs 4.2.4.2.5 & 5.2.17.5,increasing Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1 | Fuel cladding |
ML20132C627 | 17 September 1985 | Proposed Tech Spec Changes,Clarifying Actions Required When Both Containment Ventilation Dampers in Penetration Inoperable | |
ML20133C244 | 16 September 1985 | Proposed Tech Specs,Deleting Section 2.4.7 & Simplifying & Making More Stringent Applicable Conditions for Low Pressure Core Spray | Reactor Vessel Water Level Hydrostatic |
ML20129A890 | 25 June 1985 | Proposed Tech Spec Changes to Section 4.1 Requiring Reactor Shutdown to Condition 4 Prior to Mississippi River Level Exceeding 640 Ft at Facility | |
ML20211J976 | 18 June 1985 | Revised Emergency Plan Implementing Procedures,Including Issue 20 to EPP-2, Organization & Operations During Emergencies, Issue 9 to EPP-5, Estimate of Offsite Dose & Issue 5 to EPP-6 Re Sample Collection & Analysis | Grab sample FLEX |
ML20062K246 | 29 July 1982 | Seismic & Structural Analysis for Lacrosse BWR Turbine Bldg | |
ML20058G219 | 28 July 1982 | STS Pages 3/4 9-8 & 3/4 9-9 Re Refueling Operations | |
ML20062F995 | 28 July 1982 | Seismic & Structural Analysis for LACBWR Containment Bldg, Revision 0 | |
ML20062K290 | 27 July 1982 | Seismic & Stress Analysis of LACBWR 14-Inch Shutdown Condenser Vent Piping Sys | |
ML20062E037 | 1 July 1982 | Public Version of Issue 5 to Radiological Emergency Response Plan Implementing Procedure EPP-2, Organization & Operations During Emergencies | |
ML20054F217 | 9 June 1982 | Proposed Tech Spec 5.2.1.6 Re Containment Ventilation Isolation Valve Leakage Tests | |
ML20054H450 | 21 May 1982 | Public Version of Issue 1 to Emergency Plan Implementing Procedure EPP-21, Prompt Public Notification Sys | |
ML20062K317 | 22 January 1982 | Seismic & Structural Analysis for Lacrosse BWR 1-B Diesel Generator Bldg | |
ML20062K322 | 20 January 1982 | Seismic & Structural Analysis for Lacrosse BWR Shutdown Condenser Platform | |
ML20126F947 | 4 March 1981 | Model Tech Specs 3/4.0 & 3/4.4 Re RCS Operational Leakage | Non-Destructive Examination |
ML20126F747 | 31 December 1980 | Reactor Containment Bldg Integrated Leak Rate Test (ILRT) for La Crosse Boiling Water Reactor (Lacbwr),Dec 1980 | |
ML20126B391 | 21 December 1979 | Test Rept on Allis-Chalmers 6-Inch Streamseal Butterfly Valve in Air Re Nuclear Containment Isolation Valves |