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 Issue dateFromTitleProject stage
IR 05000344/19870279 July 1987NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Mendonca M
Pereira D
Insp Rept 50-344/87-27 on 870622-26.No Violations or Deviations Noted.Major Areas Inspected:Usi A-26 & Followup & Closure of Previous Insp FindingsRequest
ML20235K2519 July 1987Crutchfield D
Office of Nuclear Reactor Regulation
Requests Addl Info to Assess Safe Operation of Facility Following 1987 Refueling Outage.Concerns Expressed Re Supports Inadequate to Meet Design Loads & Original Design Loads Derived Inappropriately.Submittal of Fee Not RequiredOther
IR 05000344/198702410 July 1987NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Mendonca M
Rebecca Barr
Suh G
Insp Rept 50-344/87-24 on 870524-0725.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Piping Support & Restraint Sys & Followup on Previously Identified ItemsRequest
ML20235J39610 July 1987Portland General Electric
Cockfield D
Responds to NRC on Concerns Re safety-related Supports at Plant,Including Original Design,Derivation of Original Design Loads & Original Design Calculation for Main Steam Sys Designed for PlantOther
ML20235R88015 July 1987Portland General Electric
Cockfield D
Forwards Revised Pages to Util 870710 Response to NRC Re safety-related Piping Supports at Facility.Changes Do Not Affect Results or Conclusions of Verification Program inOther
ML20236F10727 July 1987Portland General Electric
Cockfield D
Forwards Addl Info Requested During NRC 870721-23 Review of Util Support Design Verification Program.Util Response to NRC Concerns Re Inadequate Supports,Original Design Loads & Documentation of Design Calculations DiscussedOther
ML20236H97231 July 1987Portland General Electric
Cockfield D
Forwards Addl Info Clarifying Util 870727 Response to NRC Concerns Re Design Adequacy of Piping Supports.Util Concludes That Heatup Commencement & Return to Power Operation Safe Although All Activities Not CompleteOther
ML20237H20810 August 1987ABB IMPELL CORP. (FORMERLY IMPELL CORP.)Rev 0 to 01-0300-1629, Independent QA Audit & Technical Quality Review of Trojan Nuclear Power Plant Pipe Support Verification ProgramOther
ML20237H18818 August 1987Portland General Electric
Cockfield D
Forwards Info Including Independent Audit Re Scope of Pipe Support Design Verification Program,Per 870710,15,27 & 31 Submittals.Supports Verified & short-term Program Complete. Util Will Provide Details of long-term Program by 870930Other
ML20237G62621 August 1987Crutchfield D
Office of Nuclear Reactor Regulation
Informs That Based on Info Provided,Nrc Finds That Util Adequately Evaluated Design Adequacy of Pipe Supports & Supports Will Fulfill Requirement,As Stated in Updated Fsar. NRC Concludes That Power Operation May Be ResumedOther
ML20238C6694 September 1987Portland General Electric
Cockfield D
Forwards Revised Pages of Util Re Pipe Support Design Verification Program.Ltr Revised Due to Typos Re Std Deviations in Min Rock Bolt Depth Assumption & Revised Chi- Squared ValuesOther
ML20235G80625 September 1987Chan T
Office of Nuclear Reactor Regulation
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation EnclMeeting
ML20235Q80530 September 1987Portland General Electric
Cockfield D
Forwards Pipe Support Design Verification long-term Plan,Per 870818 short-term Plan,For safety-related,large-bore Piping. Encls Include Responses to Remaining short-term Concerns, Evaluation Plan for Ae Design Activity & Ae Audit ResponseOther
ML20236A89713 October 1987Chan T
Office of Nuclear Reactor Regulation
Forwards Safety Evaluation Re Pipe Support Design Verification.Issues & Details of Pipe Support Design Verification long-term Plan Discussed in Will Be Addressed in Future CorrespondenceApproval