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Issue date | From | Title | Project stage | |
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IR 05000344/1987027 | 9 July 1987 | NRC 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 Findings | Request |
ML20235K251 | 9 July 1987 | Crutchfield 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 Required | Other |
IR 05000344/1987024 | 10 July 1987 | NRC 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 Items | Request |
ML20235J396 | 10 July 1987 | Portland 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 Plant | Other |
ML20235R880 | 15 July 1987 | Portland 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 in | Other |
ML20236F107 | 27 July 1987 | Portland 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 Discussed | Other |
ML20236H972 | 31 July 1987 | Portland 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 Complete | Other |
ML20237H208 | 10 August 1987 | ABB 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 Program | Other |
ML20237H188 | 18 August 1987 | Portland 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 870930 | Other |
ML20237G626 | 21 August 1987 | Crutchfield 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 Resumed | Other |
ML20238C669 | 4 September 1987 | Portland 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 Values | Other |
ML20235G806 | 25 September 1987 | Chan 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 Encl | Meeting |
ML20235Q805 | 30 September 1987 | Portland 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 Response | Other |
ML20236A897 | 13 October 1987 | Chan 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 Correspondence | Approval |