RS-09-050, Byron, Unit 2 - Requests for Relief for Alternate Examination Frequency - Attachments 1 Through 4
AECM-84-0043, Suppl to Final Part 21 Rept Re Failure of Qualified Cables on Transamerica Delaval Generators to Pass IEEE Flame Test Due to Inadequate Temp Rating for Cable Insulation. Initially Reported on 821214
05000458/LER-1998-002, :on 980425,failure of Two Trains of Annulus Mixing Was Noted.Caused by Problem W/Instantaneous Trip of Setpoint a & B Supply Breakers.Corrected Trip Settings & Replaced B Breaker
05000327/LER-1985-044-01, :on 851025 & 1108,safety Injection Pumps Flow Rate Failed to Meet Criteria of Tech Specs.Caused by Personnel Error.Westinghouse Recommendations for Determining Compliance Incorporated Into Instruction
05000318/LER-1985-011-01, :on 851019,while in Mode 3 Shutdown, Surveillance Test Procedure Determined 11 of 16 Main Steam Safety Valve (MSSV) Setpoints Out of Spec.Valve Setpoints Reset & Hydroset Sent to Vendor
AECM-84-0114, Forwards Response to Request for Addl Info on Hydrogen Control Re 1/4 Scale Mark III Test Facility & H2 Combustion Test Program
NUREG/CR-4661, Forwards Written Comments & Suggested Changes to Draft NUREG/CR-4661, Closeout of IE Bulletin 85-003: Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings
1CAN108901, Application for Amend to License DPR-51,clarifying Tech Spec 3.2.1.2 Re Sys Piping & Valves Necessary to Establish Flow Path from Tank to Makeup Sys
HNP-95-023, Application for Amend to License NPF-63,revising EDG SR Contained in Section 4.8.1.1.2 to Be Consistent w/NUREG-1431 New Std TS for Westinghouse Plants & Eliminating Need for Duplicate EDG Testing Being Performed
L-81-529, Forwards Results of Steam Generator Insps Conducted During Nov 1981 Outage.Insp Revealed No New Phenomena & Verified General Pattern of Denting Is within Predictable Limits. Return to Power Presents No Unresolved Safety Question
L-83-240, Responds to Generic Ltr 83-10b Re Resolution of TMI Action Plan Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Program to Close Out Item Under Development in Conjunction w/C-E Owners Group Program
DCL-90-038, Forwards Proprietary WCAP-12495 & Nonproprietary WCAP-12496, Review of Flow Peaking & Tube Fatigue in Diablo Canyon Units 1 & 2 Steam Generators Per El Murphy Aug 1989 Request