Pages that link to "ML20039C038"

The following pages link to ML20039C038:

Displayed 35 items.

• ML20087P713 ‎ (← links)
• ML20082L244 ‎ (← links)
• ML20076K323 ‎ (← links)
• ML20073M288 ‎ (← links)
• ML20073M276 ‎ (← links)
• ML20073M245 ‎ (← links)
• ML20098B777 ‎ (← links)
• ML20116E663 ‎ (← links)
• ML20112B543 ‎ (← links)
• ML20072Q703 ‎ (← links)
• ML20212M560 ‎ (← links)
• A03722, Forwards Addl Info Re Effects of Loss of Offsite Power on Steam Generator Tube Rupture & Main Steam Line Break Analyses ‎ (← links)
• TAC:49798 ‎ (← links)
• B11096, Forwards Startup Test Rept Cycle 6. Results within Acceptance Criteria W/Exception of Low Power Measurement of Control Element Assembly (CEA) Reactivity Worths.One CEA Bank Slightly in Excess of Criteria ‎ (← links)
• A03635, Forwards Info & Comments in Response to 831114 Request for Various Confirmatory Evaluations & Justification for Analytical Models Utilized in Cycle 6 Safety Analyses ‎ (← links)
• B11098, Provides Summary of Radiological Results Re Steam Generator Tube Rupture Reanalysis.Table Containing Doses for All Analyzed Cases Encl ‎ (← links)
• B10944, Forwards Suppl to Reload Safety Analyses for Cycle 6 Operation. Cycle 6 Reload Design Does Not Result in Previously Acceptable Safety Limits for Any Incident to Be Exceeded.Startup Scheduled for 831230 ‎ (← links)
• B11003, Informs That Util QA-verified 831212 Reanalysis of Steam Generator Tube Rupture Event.Reported Results Remain Valid. Verification Completed Prior to Startup for Cycle 6 ‎ (← links)
• B10960, Discusses Steam Generator Tube Rupture Reassessment for Cycle 6 Operation.Radiological Doses Will Be Increased as Result of Lower Reseat Pressure.Releases Expected to Be Significantly Below 10CFR100 Criteria ‎ (← links)
• A03323, Forwards Addl Info Re Methodology Utilized in Performing Safety Analysis Supporting Cycle 6 Operation,In Response to Question 400.5 in ‎ (← links)
• B10788, Discusses Re Proposed Revs to Tech Specs for Cycle 6 Reload.Current Tech Spec Limits Provide Acceptable Margin of Safety ‎ (← links)
• B10688, Application for Amend to License DPR-65,revising Tech Specs to Reflect Changes in Cycle 6 Reload Operating Characteristics ‎ (← links)
• ML20149E021 ‎ (← links)
• 05000336/LER-1983-007-01, /01T-0:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Caused by Failure of Analysis to Consider Impact of Automatic Valves.Analyses Will Be Docketed Shortly ‎ (← links)
• TAC:47471 ‎ (← links)
• ML20041D021 ‎ (← links)
• ML20041D019 ‎ (← links)
• ML20041D017 ‎ (← links)
• A02204, Provides Addl Info Requested by NRC to Facilitate Review of Cycle 5 Operation ‎ (← links)
• TAC:47978 ‎ (← links)
• B10353, Application to Amend License DPR-65 Incorporating Revisions to Tech Specs to Support Cycle 5.Completion of Revisions & Reanalysis Required for Item II.K.3.30 of NUREG-0737 Scheduled for 820701 ‎ (← links)
• ML20033A519 ‎ (← links)
• B10325, Forwards Reload Safety Analysis Submitted in Support of Cycle 5 Reload.Rept Includes Results of Boron Dilution,Loss of Reactor Coolant Flow,Seized Rotor Reanalysis & Control Element Assembly Ejection & Withdrawal at Critical ‎ (← links)
• A03413, Submits Addl Info Re Steam Generator Tube Rupture Event Analyzed in Support of Cycle 6 Operation,Per 830725 Request. Current Steam Generator Tube Rupture Analysis Adequate to Support Cycle 6 Operation ‎ (← links)
• A02000, Forwards Addl Info Requested in NRC Re Transient & Accident Analyses in Basic Safety Rept ‎ (← links)