ML20217M661
From kanterella
| ML20217M661 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/20/1998 |
| From: | Johnson W, Launi C, Schwartz B COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20217M645 | List: |
| References | |
| L-001166, L-001166-R02, L-1166, L-1166-R2, NUDOCS 9805050078 | |
| Download: ML20217M661 (77) | |
Similar Documents at LaSalle | |
|---|---|
Category:ARCHIVE RECORDS
MONTHYEARML20217B5921998-03-0606 March 1998
[Table view]Rev 1 to L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis ML20217M6611998-02-20020 February 1998 Rev 2 to L-001166, Post LOCA CR Auxiliary Electric Room & Offsite Dose ML20203E9021998-02-0303 February 1998 Rev 2 to L-001337, Containment Liner Leak Chase Channel Assessment IA-97-451, Plant Issues Matrix1997-12-0909 December 1997 Plant Issues Matrix ML20203J7501997-12-0909 December 1997 Plant Issues Matrix ML20197A4991997-12-0808 December 1997 Rev 1 to L-001378, Calculated Probability for Sustained Boiling in LaSalle Fuel Pools ML20199K7361997-11-21021 November 1997 Rev 0 to Calculation L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis ML20199K7111997-11-19019 November 1997 Rev 1 to Calculation L-001420, Unit 1 RWCU Room Setpoint Margin Analysis & Loop Accuracy ML20199K6111997-11-13013 November 1997 Rev 1 to Calculation L-001324, Area Ambient & Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection ML20199K5871997-11-0707 November 1997 Rev 1 to Calculation L-001281, RWCU Areas Temperature Response Due to High Energy RWCU Fluid Leakage ML20199L4091997-11-0303 November 1997 Rev 0 to L-001337, Containment Liner Leak Chase Channel Assessment ML20217C4051997-09-12012 September 1997 Rev 1 to L-001119, Vc/Ve Mixed Air Relative Humidity Calculation ML20217C3911997-06-12012 June 1997 Rev 1 to L-001166, Post LOCA Control Room,Auxiliary Electric Equipment Room & Offsite Doses ML20128Q3171996-10-18018 October 1996 Press Release III-96-64, LaSalle Nuclear Station Rated Acceptable in Three Areas, Good in Fourth Area in Latest NRC Assessment Rept ML20116B6141996-07-0303 July 1996 Rev 2 to Evaluation of H Pratt 54-Triton Xl Butterfly Valve w/H3BC Operator for Seismic Loads ML20116B5921996-07-0202 July 1996 Rev 2 to Evaluation of 36-125 Lb Crane Ferrosteel Wedge Gate Valve for Seismic Loads ML20116B5891996-07-0101 July 1996 Rev 1 to Evaluation of 54 Steel By-Pass Line - Lake Screan House. Drawings Encl ML20100P8981996-02-29029 February 1996 Main Steam Tunnel Temp Response for Linear Leakage Ramp Rate Sensitivities ML20100L3821996-02-28028 February 1996 Methodology & Acceptance Criteria ML20100L3941996-02-28028 February 1996 Thermal Expansion Values for Condenser 1CD01A ML20100L4071996-02-28028 February 1996 Rev 0 to Calculation L-000190 for LaSalle ML20100P9061996-02-28028 February 1996 Rad Monitor Dose Rates Due to Postulated Steam Tunnel Leakage ML20100L3991996-02-0606 February 1996 Condenser Bracket Design ML20100P9171996-01-16016 January 1996 Main Steam Tunnel Temp Isolation Setpoint Error Analysis ML20100P8671996-01-13013 January 1996 Main Steam Tunnel Temp Response Due to Steam Leakage W/Ventilation Sys in Operation ML20100P8761996-01-12012 January 1996 Radiological Doses Due to Postulated Steam Tunnel Leakage ML20100P9291995-12-0505 December 1995 Tunnel Main Steam Line Leak Rate Calculation ML20093D4521995-07-14014 July 1995 Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance for LaSalle Unit 1 ML20087H7931995-03-30030 March 1995 Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance ML20072R4861994-09-0808 September 1994 Commonwealth Edison Co Corporate Quality Verification Dept Audit Rept G-94-80 ML20084Q5441994-03-0404 March 1994 Ampacity Derating for Combination Thermo Lag 330-1 Matl & Darmatt Firewrap ML20096E9271992-05-12012 May 1992 Rev 1 to Main CR Temp Transient Following Sbo ML20096E9381992-05-12012 May 1992 Rev 1 to RCIC Pump Room Temp Transient Following Sbo ML20096E9311992-05-11011 May 1992 Rev 1 to Auxiliary Electric Equipment Room Temp Transients During Sbo ML20096E9451992-05-11011 May 1992 Rev 1 to Drywell Temp Transient Following Sbo ML20096E9591992-05-11011 May 1992 Rev 1 to Suppression Pool Temp Transient Following Sbo ML20096E9721992-05-11011 May 1992 Rev 0 to Evaluation of NPSH Requirements for Hpcs,Rhr & RCIC Pumps & Backpressure Limitations of RCIC Turbine Following Sbo ML20096E9701992-05-11011 May 1992 Rev 0 to Calculation for EQ Impact Due to SBO Conditions ML20085M5221991-11-11011 November 1991 Question & Answer Responses to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20247J0141988-11-0808 November 1988 Drywell Pressure Instrument Loop Failure Analysis ML20247J0201988-11-0808 November 1988 Reactor Water Level Instrument Loop Failure Analysis IA-87-376, List of Rmiep & Methods Repts W/Corresponding Scheduled Date1987-08-11011 August 1987 List of Rmiep & Methods Repts W/Corresponding Scheduled Date ML20236M7211987-08-11011 August 1987 List of Rmiep & Methods Repts W/Corresponding Scheduled Date ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20199K6661986-05-0707 May 1986 Rev 1 to Calculation 3C7-1184-001, ECCS Room Leak Detection Setpoints ML20132F8891985-09-20020 September 1985 Power Plant Exam Results Summary Sheets.Info Deleted IA-85-442, Package of Operator Exam Results Summary Sheets1985-07-18018 July 1985 Package of Operator Exam Results Summary Sheets ML20134L5811985-07-18018 July 1985 Package of Operator Exam Results Summary Sheets ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20084K1461984-03-31031 March 1984 Audit of Nuclear Plant Tech Specs,Lasalle County Station, Unit 2 1998-03-06 Category:OPERATIONS SUPPORT-CALCULATIONS MONTHYEARML20217B5921998-03-0606 March 1998
[Table view]Rev 1 to L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis ML20217M6611998-02-20020 February 1998 Rev 2 to L-001166, Post LOCA CR Auxiliary Electric Room & Offsite Dose ML20203E9021998-02-0303 February 1998 Rev 2 to L-001337, Containment Liner Leak Chase Channel Assessment ML20197A4991997-12-0808 December 1997 Rev 1 to L-001378, Calculated Probability for Sustained Boiling in LaSalle Fuel Pools ML20199K7361997-11-21021 November 1997 Rev 0 to Calculation L-001443, Reactor Water Cleanup High Flow Isolation Error Analysis ML20199K7111997-11-19019 November 1997 Rev 1 to Calculation L-001420, Unit 1 RWCU Room Setpoint Margin Analysis & Loop Accuracy ML20199K6111997-11-13013 November 1997 Rev 1 to Calculation L-001324, Area Ambient & Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection ML20199K5871997-11-0707 November 1997 Rev 1 to Calculation L-001281, RWCU Areas Temperature Response Due to High Energy RWCU Fluid Leakage ML20199L4091997-11-0303 November 1997 Rev 0 to L-001337, Containment Liner Leak Chase Channel Assessment ML20217C4051997-09-12012 September 1997 Rev 1 to L-001119, Vc/Ve Mixed Air Relative Humidity Calculation ML20217C3911997-06-12012 June 1997 Rev 1 to L-001166, Post LOCA Control Room,Auxiliary Electric Equipment Room & Offsite Doses ML20116B6141996-07-0303 July 1996 Rev 2 to Evaluation of H Pratt 54-Triton Xl Butterfly Valve w/H3BC Operator for Seismic Loads ML20116B5921996-07-0202 July 1996 Rev 2 to Evaluation of 36-125 Lb Crane Ferrosteel Wedge Gate Valve for Seismic Loads ML20116B5891996-07-0101 July 1996 Rev 1 to Evaluation of 54 Steel By-Pass Line - Lake Screan House. Drawings Encl ML20100P8981996-02-29029 February 1996 Main Steam Tunnel Temp Response for Linear Leakage Ramp Rate Sensitivities ML20100L3821996-02-28028 February 1996 Methodology & Acceptance Criteria ML20100L3941996-02-28028 February 1996 Thermal Expansion Values for Condenser 1CD01A ML20100L4071996-02-28028 February 1996 Rev 0 to Calculation L-000190 for LaSalle ML20100P9061996-02-28028 February 1996 Rad Monitor Dose Rates Due to Postulated Steam Tunnel Leakage ML20100L3991996-02-0606 February 1996 Condenser Bracket Design ML20100P9171996-01-16016 January 1996 Main Steam Tunnel Temp Isolation Setpoint Error Analysis ML20100P8671996-01-13013 January 1996 Main Steam Tunnel Temp Response Due to Steam Leakage W/Ventilation Sys in Operation ML20100P8761996-01-12012 January 1996 Radiological Doses Due to Postulated Steam Tunnel Leakage ML20100P9291995-12-0505 December 1995 Tunnel Main Steam Line Leak Rate Calculation ML20093D4521995-07-14014 July 1995 Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance for LaSalle Unit 1 ML20087H7931995-03-30030 March 1995 Evaluation of Effect of Relaxing LaSalle Mainsteam SRV Overpressurization Setpoint Tolerance ML20084Q5441994-03-0404 March 1994 Ampacity Derating for Combination Thermo Lag 330-1 Matl & Darmatt Firewrap ML20096E9271992-05-12012 May 1992 Rev 1 to Main CR Temp Transient Following Sbo ML20096E9381992-05-12012 May 1992 Rev 1 to RCIC Pump Room Temp Transient Following Sbo ML20096E9311992-05-11011 May 1992 Rev 1 to Auxiliary Electric Equipment Room Temp Transients During Sbo ML20096E9451992-05-11011 May 1992 Rev 1 to Drywell Temp Transient Following Sbo ML20096E9591992-05-11011 May 1992 Rev 1 to Suppression Pool Temp Transient Following Sbo ML20096E9721992-05-11011 May 1992 Rev 0 to Evaluation of NPSH Requirements for Hpcs,Rhr & RCIC Pumps & Backpressure Limitations of RCIC Turbine Following Sbo ML20096E9701992-05-11011 May 1992 Rev 0 to Calculation for EQ Impact Due to SBO Conditions ML20247J0201988-11-0808 November 1988 Reactor Water Level Instrument Loop Failure Analysis ML20247J0141988-11-0808 November 1988 Drywell Pressure Instrument Loop Failure Analysis ML20199K6661986-05-0707 May 1986 Rev 1 to Calculation 3C7-1184-001, ECCS Room Leak Detection Setpoints ML20199L3951981-08-21021 August 1981 Rev 0 to 164, Containment Leak Test Channel Reassessment for Loads 1998-03-06 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML20217M661&oldid=3197408"