List of Rmiep & Methods Repts W/Corresponding Scheduled Date| ML20236M721 |
| Person / Time |
|---|
| Site: |
LaSalle  |
|---|
| Issue date: |
08/11/1987 |
|---|
| From: |
NRC |
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| To: |
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| Shared Package |
|---|
| ML20236M713 |
List: |
|---|
| References |
|---|
| FOIA-87-376, RTR-NUREG-CR-4831, RTR-NUREG-CR-4832, RTR-NUREG-CR-4833, RTR-NUREG-CR-4834, RTR-NUREG-CR-4835, RTR-NUREG-CR-4836, RTR-NUREG-CR-4837, RTR-NUREG-CR-4838, RTR-NUREG-CR-4839, RTR-NUREG-CR-4840 NUDOCS 8708110203 |
| Download: ML20236M721 (1) |
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Category:ARCHIVE RECORDS
MONTHYEARML20217B5921998-03-0606 March 1998
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
[Table view]
Category:PACKAGE OF NONCODED MATERIAL
[Table view] |
Text
, - _ _ _ _ _ - - _ . _ _ _ . . -_
t I
= RMIEP and Methods Reports .
l 1
Scheduled l
' Date NUREG/CR-4831 Executive Summary for RMIEP l NUREG/CR-4832 LaSalle PRA. l Vol. 1. Summary Report. January 1988
- 2. Integrated Uncertainty Analysis. November 1987
- 3. Results of Quantification of Septem.ier 1987 i Internal Events. l
- 4. Initiating Events, Event Trees, September 1987 Fault Trees. l S. Data, Quantification, Uncertainty, September 1987 HRA.
- 6. System Descriptions. September 1987
- 7. Results of External Event Screening September 1987 l Quant. ,
8&9. Seismic. September 1987 l l
- 10. Fire. September 1987
- 11. Flood. September 1987 l NUREG/CR-4833 Summary of Methodological Insights from RMIEP. January 1988 NUREG/CR-4834 Recovery Model. ;
Vol. 1 August 1987 1 Vol. 2 September 1987 NUREG/CR-4835 HRA Report. September 1987
- NUREG/CR-4836 Uncertainty Methods Report. October 1987 NUREG/CR-4837 CCF Procedures. November 1987 NUREG/CR-4838 CCF Experience. December 1987 NUREG/CR-4839 Integrated Quantification Report. February 1988 NUREG/CR 4840 Methods for External Event Screening Quantification November 1987 8708110203 870006 PDR FOIA 5HOLLYB7-376 PDR i
L_.,_ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . _ . _ _ . _ _ _ _ _ . - _ _