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Issue date | Title | Topic | |
---|---|---|---|
ML20217B592 | 6 March 1998 | Rev 1 to L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis | |
ML20217M661 | 20 February 1998 | Rev 2 to L-001166, Post LOCA CR Auxiliary Electric Room & Offsite Dose | |
ML20203E902 | 3 February 1998 | Rev 2 to L-001337, Containment Liner Leak Chase Channel Assessment | |
IA-97-451, Plant Issues Matrix | 9 December 1997 | Plant Issues Matrix | Hot Short Safe Shutdown Unanalyzed Condition Boric Acid Loop seal Packing leak High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Stroke time Weld Overlay Anchor Darling Emergency Lighting Locked High Radiation Area Foreign Material Exclusion Scram Discharge Volume Annual Radiological Environmental Operating Report Battery sizing Earthquake Fire Protection Program Fire Watch Downpower Reverse polarity |
ML20203J750 | 9 December 1997 | Plant Issues Matrix | Hot Short Safe Shutdown Unanalyzed Condition Boric Acid Loop seal Packing leak High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Stroke time Weld Overlay Anchor Darling Emergency Lighting Locked High Radiation Area Foreign Material Exclusion Scram Discharge Volume Annual Radiological Environmental Operating Report Battery sizing Earthquake Fire Protection Program Fire Watch Downpower Reverse polarity |
ML20197A499 | 8 December 1997 | Rev 1 to L-001378, Calculated Probability for Sustained Boiling in LaSalle Fuel Pools | Time to boil |
ML20199K736 | 21 November 1997 | Rev 0 to Calculation L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis | |
ML20199K711 | 19 November 1997 | Rev 1 to Calculation L-001420, Unit 1 RWCU Room Setpoint Margin Analysis & Loop Accuracy | |
ML20199K611 | 13 November 1997 | Rev 1 to Calculation L-001324, Area Ambient & Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection | Safe Shutdown Reactor Vessel Water Level |
ML20199K587 | 7 November 1997 | Rev 1 to Calculation L-001281, RWCU Areas Temperature Response Due to High Energy RWCU Fluid Leakage | |
ML20199L409 | 3 November 1997 | Rev 0 to L-001337, Containment Liner Leak Chase Channel Assessment | |
ML20217C405 | 12 September 1997 | Rev 1 to L-001119, Vc/Ve Mixed Air Relative Humidity Calculation | |
ML20217C391 | 12 June 1997 | Rev 1 to L-001166, Post LOCA Control Room,Auxiliary Electric Equipment Room & Offsite Doses | |
ML20128Q317 | 18 October 1996 | Press Release III-96-64, LaSalle Nuclear Station Rated Acceptable in Three Areas, Good in Fourth Area in Latest NRC Assessment Rept | Systematic Assessment of Licensee Performance |
ML20116B614 | 3 July 1996 | Rev 2 to Evaluation of H Pratt 54-Triton Xl Butterfly Valve w/H3BC Operator for Seismic Loads | |
ML20116B592 | 2 July 1996 | Rev 2 to Evaluation of 36-125 Lb Crane Ferrosteel Wedge Gate Valve for Seismic Loads | Hydrostatic B.5.b Mitigating Strategies Weak link |
ML20116B589 | 1 July 1996 | Rev 1 to Evaluation of 54 Steel By-Pass Line - Lake Screan House. Drawings Encl | |
ML20100P898 | 29 February 1996 | Main Steam Tunnel Temp Response for Linear Leakage Ramp Rate Sensitivities | GOTHIC |
ML20100L394 | 28 February 1996 | Thermal Expansion Values for Condenser 1CD01A | |
ML20100L382 | 28 February 1996 | Methodology & Acceptance Criteria | |
ML20100L407 | 28 February 1996 | Rev 0 to Calculation L-000190 for LaSalle | |
ML20100P906 | 28 February 1996 | Rad Monitor Dose Rates Due to Postulated Steam Tunnel Leakage | |
ML20100L399 | 6 February 1996 | Condenser Bracket Design | |
ML20100P917 | 16 January 1996 | Main Steam Tunnel Temp Isolation Setpoint Error Analysis | |
ML20100P867 | 13 January 1996 | Main Steam Tunnel Temp Response Due to Steam Leakage W/Ventilation Sys in Operation | |
ML20100P876 | 12 January 1996 | Radiological Doses Due to Postulated Steam Tunnel Leakage | Offsite Dose Calculation Manual |
ML20100P929 | 5 December 1995 | Tunnel Main Steam Line Leak Rate Calculation | |
ML20093D452 | 14 July 1995 | Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance for LaSalle Unit 1 | Unanalyzed Condition Shutdown Margin Reactor Vessel Water Level Fuel cladding |
ML20087H793 | 30 March 1995 | Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance | |
ML20072R486 | 8 September 1994 | Commonwealth Edison Co Corporate Quality Verification Dept Audit Rept G-94-80 | Fire Barrier |
ML20084Q544 | 4 March 1994 | Ampacity Derating for Combination Thermo Lag 330-1 Matl & Darmatt Firewrap | Fire Barrier Coatings |
ML20096E927 | 12 May 1992 | Rev 1 to Main CR Temp Transient Following Sbo | |
ML20096E938 | 12 May 1992 | Rev 1 to RCIC Pump Room Temp Transient Following Sbo | |
ML20096E970 | 11 May 1992 | Rev 0 to Calculation for EQ Impact Due to SBO Conditions | |
ML20096E931 | 11 May 1992 | Rev 1 to Auxiliary Electric Equipment Room Temp Transients During Sbo | |
ML20096E945 | 11 May 1992 | Rev 1 to Drywell Temp Transient Following Sbo | |
ML20096E959 | 11 May 1992 | Rev 1 to Suppression Pool Temp Transient Following Sbo | Reactor Vessel Water Level |
ML20096E972 | 11 May 1992 | Rev 0 to Evaluation of NPSH Requirements for Hpcs,Rhr & RCIC Pumps & Backpressure Limitations of RCIC Turbine Following Sbo | Hydrostatic |
ML20085M522 | 11 November 1991 | Question & Answer Responses to NUMARC Survey in Support of NRC License Renewal Rulemaking | Weld Overlay License Renewal Scaffolding |
ML20247J014 | 8 November 1988 | Drywell Pressure Instrument Loop Failure Analysis | |
ML20247J020 | 8 November 1988 | Reactor Water Level Instrument Loop Failure Analysis | |
IA-87-376, List of Rmiep & Methods Repts W/Corresponding Scheduled Date | 11 August 1987 | List of Rmiep & Methods Repts W/Corresponding Scheduled Date | |
ML20236M721 | 11 August 1987 | List of Rmiep & Methods Repts W/Corresponding Scheduled Date | |
ML20151M960 | 20 July 1987 | Package of NRC Administered Requalification Exam Results Summary | |
ML20199K666 | 7 May 1986 | Rev 1 to Calculation 3C7-1184-001, ECCS Room Leak Detection Setpoints | |
ML20132F889 | 20 September 1985 | Power Plant Exam Results Summary Sheets.Info Deleted | |
IA-85-442, Package of Operator Exam Results Summary Sheets | 18 July 1985 | Package of Operator Exam Results Summary Sheets | |
ML20134L581 | 18 July 1985 | Package of Operator Exam Results Summary Sheets | |
ML20129F483 | 9 May 1985 | Package of Compilations of Results of Operator Licensing & Requalification Exams | |
ML20084K146 | 31 March 1984 | Audit of Nuclear Plant Tech Specs,Lasalle County Station, Unit 2 |