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| Issue date | Title | Topic | |
|---|---|---|---|
| ML19332B580 | 30 September 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: La Salle-1/-2, Technical Evaluation Rept | |
| ML20010E775 | 31 July 1981 | Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept | Post Accident Monitoring Scram Discharge Volume |
| ML20012E267 | 31 March 1990 | Risk Sensitivity to Human Error in the Lasalle PRA | |
| ML20042D087 | 4 August 1988 | Simulations of BWR Power Oscillations W/O Scram, Informal Rept | Fuel cladding |
| ML20045B904 | 31 May 1993 | Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C | Probabilistic Risk Assessment |
| ML20045B948 | 31 May 1993 | Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G | |
| ML20058E891 | 30 November 1993 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis | |
| ML20058K086 | 31 July 1989 | Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to LaSalle County Station,Unit 2 | Packing leak Weld Overlay |
| ML20058K092 | 31 July 1989 | Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to Lasalle County Station,Unit 1 | Packing leak Weld Overlay |
| ML20065B713 | 30 June 1982 | Control of Heavy Loads at Nuclear Power Plants LaSalle Units 1 & 2 | Safe Shutdown Control of Heavy Loads |
| ML20076J271 | 31 May 1983 | Control of Heavy Loads at Nuclear Power Plants,Lasalle Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept | Safe Shutdown Control of Heavy Loads |
| ML20097H316 | 30 June 1992 | Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) | |
| ML20099D528 | 31 July 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary | Reactor Vessel Water Level Ultimate heat sink Fire Barrier Internal Flooding Probabilistic Risk Assessment Earthquake Fire Watch |
| ML20099D625 | 31 July 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification | |
| ML20101G154 | 31 December 1984 | Conformance to Reg Guide 1.97,LaSalle County Station,Units 1 & 2 | Grab sample Fuel cladding |
| ML20105C763 | 31 August 1992 | Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) | Ultimate heat sink Probabilistic Risk Assessment Earthquake |
| ML20105C817 | 31 August 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report | |
| ML20105C822 | 31 August 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices | Probabilistic Risk Assessment |
| ML20106H126 | 12 December 1995 | IPE Insight Rept NUREG-1150 Plants | Ultimate heat sink Probabilistic Risk Assessment Containment Hardened Vent |
| ML20113H989 | 31 July 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis | |
| ML20116J479 | 31 October 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis | Safe Shutdown Internal Flooding Probabilistic Risk Assessment VT-2 |
| ML20116J531 | 31 October 1992 | Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation | Reactor Vessel Water Level Ultimate heat sink Probabilistic Risk Assessment Feedwater Controller Failure |
| ML20116J655 | 31 October 1992 | Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations | |
| ML20126F254 | 26 August 1982 | Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 | |
| ML20134J509 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station & WPPSS-2 | |
| ML20141N605 | 14 January 1986 | SPDS Progress Review,Lasalle,Units 1 & 2 | Reactor Vessel Water Level Operating Basis Earthquake |
| ML20150A864 | 31 May 1988 | Pump & Valve Inservice Testing Program,Lasalle County Station,Units 1 & 2 | High Radiation Area Stroke time Cold shutdown justification Power Operated Valves Fuel cladding |
| ML20153D210 | 31 January 1988 | Approaches to Uncertainty Analysis in Probabilistic Risk Assessment | Mission time Probabilistic Risk Assessment Earthquake |
| ML20155D627 | 14 February 1986 | Mod Program Controls, Based on 860210-14 Review | Scram Discharge Volume |
| ML20211F030 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) | |
| ML20214G959 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants | |
| ML20215L966 | 30 April 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs for All Other Safety-Related Components, La Salle Units 1 & 2, Informal Rept | |
| ML20236X287 | 31 October 1987 | Fire Environment Determination in the Lasalle Nuclear Power Plant Control Room | Fire Barrier Probabilistic Risk Assessment Earthquake |
| ML20244D398 | 10 July 1985 | Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.1, `Post-Trip Review:Program Description & Procedure' for La Salle County Station.. | |
| ML20244D441 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station Units 1 & 2 & Washington Nuclear Plant Unit 2. Contains Info for LaSalle | |
| ML20246B815 | 30 April 1989 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept |