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ML09217018430 September 20082009 Dresden Initial License Examination Proposed Simulator Scenarios
ML1022304418 March 2010Initial License Exam, Scenarios
ML11202A18629 June 2011Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 7.0, Instrumentation and Controls
ML11202A20529 June 2011Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
ML12284A48026 September 20122012 Dresden Nuclear Power Plant Initial License Examination Proposed Simulator Scenarios
ML13128A0567 May 2013IR 05000237-13-002, 05000249-13-002; 01/01/2013 - 03/31/2013; Dresden Nuclear Power Station, Units 2 & 3; Adverse Weather Protection and Identification and Resolution of Problem
ML13207A04026 July 2013EN-13-026, Issuance of Final Significance Determination and Notice of Violation to Exelon Generation Company, LLC, Dresden Nuclear Power Station, Units 2 & 3
ML15324A43917 December 2015Issuance of Amendments (CAC Nos. MF5471-MF5476)
ML16111A10411 May 2016Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644)
ML16209A21826 July 2016Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML16280A4026 October 2016License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML17187A80531 January 1993Suppl 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.
ML17192A67920 December 1979Emergency Procedure DGA-20,Revision 0, Relief Valve Failure.
ML17252A75330 November 1992Lpci/Containment Cooling Sys Evaluation.
ML17271A10621 August 20172017 Dresden Initial License Exam Simulator Scenarios
ML17271A38121 August 2017Simulator Scenarios
ML17272A7838 January 2018Issuance of Amendments to Adopt TSTF-542 TS Changes (CAC Nos. MF9295 and MF9296; EPID L-2017-LLA-0176)
ML19183A10321 June 2019Attachments a to G
ML19301A3394 December 2019Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits
ML20059B82024 May 1993Partial Response to Request for Info.App E Info in Pdr. Forwards App D Documents Which Will Be Available in PDR
ML20066E05913 September 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-249/82-08.Corrective Actions:Typed Version of Calibr Records for Flow Meter Used During Induced Leakage Phase of Integrated Leak Rate Test Received from Vendor
ML20087H8652 May 1995Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20106A62215 September 1992Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20113B60020 June 1996Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20125D6388 December 1992Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20137H24623 August 1985Exam Rept 50-237/OL-85-02 on 850610-14.Exam results:11 Candidates Took Exam & 7 Passed
ML20148S4761 July 1997Responds to NRC Re Violations Noted in Insp Repts 50-010/97-11,50-237/97-11 & 50-249/97-11.Corrective Actions: Problem Identification Form Generated & Maintenance Rule Expert Panel Convened
ML20149E74811 July 1997Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-11, 50-237/97-11 & 50-249/97-11.Corrective Actions Reviewed & Will Be Examined During Future Inspections
ML20150B46720 June 1988Summary of 880608 Facility Site Visit to Attend Exit Meeting for Insp of Emergency Operating Procedures (EOP) Performed by Assigned Region I EOP Team
ML20154A39828 September 1984Analysis of Dresden Units 2 & 3 Operation W/One Relief Valve Out-of-Svc
ML20154A41313 July 1988Extended Operating Domain/Equipment Out-of-Svc Analysis for Dresden Units 2 & 3
ML20198N30324 October 1997Insp Repts 50-010/97-13,50-237/97-13 & 50-249/97-13 on 970715-0827.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support
ML20205A6455 August 1986Exam Rept 50-237/OL-86-02 at Units 1 & 2 on 860624-27.Exam Results:One of Three Senior Reactor Operator Candidates & One of Three Reactor Candidates Passed.Master Copy of Exam Encl
ML20213F06410 November 1986Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20323A25418 November 2020Markup of Proposed Technical Specifications Bases Pages
ML21179A02821 June 20214 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems
ML21179A03321 June 20214 to Final Safety Analysis Report, Chapter 4, Reactor
ML21179A03421 June 20214 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML21179A03721 June 20214 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features
ML21179A03821 June 20214 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML21179A03921 June 20214 to Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML21179A04421 June 20214 to Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis
ML21179A04821 June 2021Technical Requirements Manual (TRM)
ML21179A05221 June 2021Amendment 23 to Fire Protection Report, Volume 2 Safe Shutdown Analysis
ML22215A18514 May 2021April 2021 Administered Scenarios
ML22216A18914 May 2021April 2021 Proposed Scenarios
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
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