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 Issue dateTitleTopic
ML20217B5926 March 1998Rev 1 to L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis
ML20217M66120 February 1998Rev 2 to L-001166, Post LOCA CR Auxiliary Electric Room & Offsite Dose
ML20203E9023 February 1998Rev 2 to L-001337, Containment Liner Leak Chase Channel Assessment
IA-97-451, Plant Issues Matrix9 December 1997Plant Issues MatrixHot 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
ML20203J7509 December 1997Plant Issues MatrixHot 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
ML20197A4998 December 1997Rev 1 to L-001378, Calculated Probability for Sustained Boiling in LaSalle Fuel PoolsTime to boil
ML20199K73621 November 1997Rev 0 to Calculation L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis
ML20199K71119 November 1997Rev 1 to Calculation L-001420, Unit 1 RWCU Room Setpoint Margin Analysis & Loop Accuracy
ML20199K61113 November 1997Rev 1 to Calculation L-001324, Area Ambient & Differential Temperature Design Basis Calculations for Reactor Coolant Leak DetectionSafe Shutdown
Reactor Vessel Water Level
ML20199K5877 November 1997Rev 1 to Calculation L-001281, RWCU Areas Temperature Response Due to High Energy RWCU Fluid Leakage
ML20199L4093 November 1997Rev 0 to L-001337, Containment Liner Leak Chase Channel Assessment
ML20217C40512 September 1997Rev 1 to L-001119, Vc/Ve Mixed Air Relative Humidity Calculation
ML20217C39112 June 1997Rev 1 to L-001166, Post LOCA Control Room,Auxiliary Electric Equipment Room & Offsite Doses
ML20128Q31718 October 1996Press Release III-96-64, LaSalle Nuclear Station Rated Acceptable in Three Areas, Good in Fourth Area in Latest NRC Assessment ReptSystematic Assessment of Licensee Performance
ML20116B6143 July 1996Rev 2 to Evaluation of H Pratt 54-Triton Xl Butterfly Valve w/H3BC Operator for Seismic Loads
ML20116B5922 July 1996Rev 2 to Evaluation of 36-125 Lb Crane Ferrosteel Wedge Gate Valve for Seismic LoadsHydrostatic
B.5.b Mitigating Strategies
Weak link
ML20116B5891 July 1996Rev 1 to Evaluation of 54 Steel By-Pass Line - Lake Screan House. Drawings Encl
ML20100P89829 February 1996Main Steam Tunnel Temp Response for Linear Leakage Ramp Rate SensitivitiesGOTHIC
ML20100L39428 February 1996Thermal Expansion Values for Condenser 1CD01A
ML20100L38228 February 1996Methodology & Acceptance Criteria
ML20100L40728 February 1996Rev 0 to Calculation L-000190 for LaSalle
ML20100P90628 February 1996Rad Monitor Dose Rates Due to Postulated Steam Tunnel Leakage
ML20100L3996 February 1996Condenser Bracket Design
ML20100P91716 January 1996Main Steam Tunnel Temp Isolation Setpoint Error Analysis
ML20100P86713 January 1996Main Steam Tunnel Temp Response Due to Steam Leakage W/Ventilation Sys in Operation
ML20100P87612 January 1996Radiological Doses Due to Postulated Steam Tunnel LeakageOffsite Dose Calculation Manual
ML20100P9295 December 1995Tunnel Main Steam Line Leak Rate Calculation
ML20093D45214 July 1995Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance for LaSalle Unit 1Unanalyzed Condition
Shutdown Margin
Reactor Vessel Water Level
Fuel cladding
ML20087H79330 March 1995Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance
ML20072R4868 September 1994Commonwealth Edison Co Corporate Quality Verification Dept Audit Rept G-94-80Fire Barrier
ML20084Q5444 March 1994Ampacity Derating for Combination Thermo Lag 330-1 Matl & Darmatt FirewrapFire Barrier
Coatings
ML20096E92712 May 1992Rev 1 to Main CR Temp Transient Following Sbo
ML20096E93812 May 1992Rev 1 to RCIC Pump Room Temp Transient Following Sbo
ML20096E97011 May 1992Rev 0 to Calculation for EQ Impact Due to SBO Conditions
ML20096E93111 May 1992Rev 1 to Auxiliary Electric Equipment Room Temp Transients During Sbo
ML20096E94511 May 1992Rev 1 to Drywell Temp Transient Following Sbo
ML20096E95911 May 1992Rev 1 to Suppression Pool Temp Transient Following SboReactor Vessel Water Level
ML20096E97211 May 1992Rev 0 to Evaluation of NPSH Requirements for Hpcs,Rhr & RCIC Pumps & Backpressure Limitations of RCIC Turbine Following SboHydrostatic
ML20085M52211 November 1991Question & Answer Responses to NUMARC Survey in Support of NRC License Renewal RulemakingWeld Overlay
License Renewal
Scaffolding
ML20247J0148 November 1988Drywell Pressure Instrument Loop Failure Analysis
ML20247J0208 November 1988Reactor Water Level Instrument Loop Failure Analysis
IA-87-376, List of Rmiep & Methods Repts W/Corresponding Scheduled Date11 August 1987List of Rmiep & Methods Repts W/Corresponding Scheduled Date
ML20236M72111 August 1987List of Rmiep & Methods Repts W/Corresponding Scheduled Date
ML20151M96020 July 1987Package of NRC Administered Requalification Exam Results Summary
ML20199K6667 May 1986Rev 1 to Calculation 3C7-1184-001, ECCS Room Leak Detection Setpoints
ML20132F88920 September 1985Power Plant Exam Results Summary Sheets.Info Deleted
IA-85-442, Package of Operator Exam Results Summary Sheets18 July 1985Package of Operator Exam Results Summary Sheets
ML20134L58118 July 1985Package of Operator Exam Results Summary Sheets
ML20129F4839 May 1985Package of Compilations of Results of Operator Licensing & Requalification Exams
ML20084K14631 March 1984Audit of Nuclear Plant Tech Specs,Lasalle County Station, Unit 2