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TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES

S.2(s) +, S.1(s) +, S.1(o) +  and S.2(t) +

05000245  +  and 00245  +

ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +, ML20059C416 +...

A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof +, B12955, Provides NRC W/Plans for Mods Re Degraded Grid Protection for Class 1E Power Sys.Delays Occurred as Result of Identification of Significant Concerns During Review. Requests NRC Initiation of Review of Design +, B13080, Responds to 881116 Request for Addl Info Re Spent Fuel Pool Capacity Expansion.Evaluation of Resultant Gaps & Refinement of Seismic Displacement Analysis Performed to Reconcile as-fabricated Condition.W/Revised Module Layout & Addl Info +, A09768, Informs That Review of Issues Re Employee Concerns for Allegation RI-91-A-0079 Complete.Comments Encl +, A09920, Discusses Review of R1-91-A-0219 Re Various Activities at Millstone Unit 2.W/related Matl +, B13667, Provides Info Re Loss of Normal Power Logic.Basic Logic Design in Place Since Initial Licensing of Plant +, ML20054K055 +, 05000336/LER-1988-008, :on 880408,control Element Assembly (CEA) 22 Dropped Into Core & on 890409,CEA 4 Dropped Into Core.Caused by Overheating of Upper Gripper Coil Due to Air Flow Blockage of Hx.Coils & Loose Wire Replaced +, 05000245/LER-1992-027, :on 921029,determined That Certain Historical Conditions Involving Open/Unsealed Fire Barrier Not Reported to Nrc.Caused by Incorrect Interpretation of Requirements. Reporting Requirements Discussed at Meeting +, 05000336/LER-1993-019, :on 930812,reactor Trip Occurred Due to Low SG Level.Conducted Shift Briefing of Event to Operating Shift While Assuming Watch.Briefing Included Listed Requirements for Subsequent Specific start-up +  and 05000336/LER-1990-010-02, :on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door Reinforced +

Safe Shutdown +, Probabilistic Risk Assessment +, Reserve Station Service Transformer +  and Manual Operator Action +