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| Issue date | Title | Topic | |
|---|---|---|---|
| ML17187A805 | 31 January 1993 | Suppl 1 to GENE-770-26-1092, Long Term Containment Response to DBA-LOCA w/65 Fdegrees F Svc Water Temperature,80 Degrees F Initial Pool Temperature & Initiation of Containment Cooling at 1800 Seconds. | Reactor Vessel Water Level Fuel cladding |
| ML17252A753 | 30 November 1992 | Lpci/Containment Cooling Sys Evaluation. | Reactor Vessel Water Level Coatings Turbine Missile Flow Induced Vibration |
| ML20065Q853 | 30 November 1990 | Rev 0 to, Comm Ed Topical Benchmark of BWR Nuclear Design Methods | |
| ML20154A413 | 13 July 1988 | Extended Operating Domain/Equipment Out-of-Svc Analysis for Dresden Units 2 & 3 | Reactor Vessel Water Level Anticipated operational occurrence Feedwater Controller Failure Power change |
| ML20147F410 | 9 February 1988 | Rev 49 to CE-1-A, QA Program for Nuclear Generating Stations | |
| ML20154A402 | 28 September 1987 | LOCA-ECCS Analysis for Dresden Units During Single Loop Operation W/Advanced Nuclear Fuels Corp Fuel | FLEX Fuel cladding |
| ML20205F271 | 31 August 1985 | Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16 to, LOCA Analysis Rept for Dresden Units 2,3 & Quad Cities 1,2 Nuclear Power Stations | Fuel cladding |
| ML20106A648 | 31 January 1985 | Errata & Addenda Sheet 13,replacing Pages v/vi,3-2,4-3, 4-15 & 4-16 to, LOCA Anaysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | Fuel cladding |
| ML20137F033 | 15 January 1985 | Rev 1 to Criticality Safety Analysis,Dresden 2,3 Spent Fuels Storage Pool W/Exxon Nuclear Co,Inc 9x9 Reload Fuel | |
| ML20154A398 | 28 September 1984 | Analysis of Dresden Units 2 & 3 Operation W/One Relief Valve Out-of-Svc | Reactor Vessel Water Level |
| ML20076G957 | 31 August 1983 | Cycle 9 Plant Transient Analysis | Stroke time Anticipated operational occurrence Power Operated Valves Power change |
| ML20076H058 | 1 August 1983 | Revised Mplhgr Analysis Using Exxon Nuclear Corp Exem Evaluation Model | FLEX |
| ML20106A605 | 30 April 1983 | Errata & Addenda Sheet 10,replacing Page 4-11 to, LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
| ML20071Q059 | 7 December 1982 | Nonproprietary Version of Revision 1 to Plant Transient Analysis for Dresden Unit 2,Cycle 9 | Stroke time Anticipated operational occurrence Power-Operated Valves Power change |
| ML20071Q036 | 2 December 1982 | to Dresden Unit 2 LOCA Analysis Using Exem/Bwr Evaluation Model MAPLHGR Results | FLEX |
| ML20069J554 | 30 September 1982 | Errata & Addenda Sheet 8,replacing Page 4-10 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
| ML20063C487 | 31 July 1982 | Errata & Addenda Sheet 7,replacing Pages 4-11 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
| ML20039G953 | 31 December 1981 | Cycle 8 Reload Analysis, Revision 1 | Shutdown Margin Anticipated operational occurrence Feedwater Controller Failure Fuel cladding |
| ML20039G956 | 23 December 1981 | 3,Cycle 8 Plant Transient Analysis Rept. | |
| ML17194A065 | 31 July 1981 | Errata & Addenda Sheet 6,replacing Pages V/VI,3-1,3-2,4-3 & 4-14,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations. | |
| ML17194A063 | 31 May 1981 | Errata & Addenda Sheet 5,replacing Pages V/VI,3-1/3-2,4-10, 4-12,4-13 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations. | |
| ML20126J695 | 31 March 1981 | Control Blade Exam Results & Response to Item 4 of IE Bulletin 79-26 | |
| ML19343A990 | 13 November 1980 | Revised Page 4-8 to LOCA Analysis Rept. Supplemental Discussion of NEDO-24855 Encl | |
| ML19250B999 | 31 December 1978 | Load Line Limit Analysis License Amend Submittal. |