Letter Sequence Approval |
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MONTHYEARIR 05000344/19870271987-07-0909 July 1987
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
Project stage: Request
ML20235K2511987-07-0909 July 1987
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
Project stage: Other
ML20235J3961987-07-10010 July 1987
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
Project stage: Other
ML20235R8801987-07-15015 July 1987
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
Project stage: Other
ML20236F1071987-07-27027 July 1987
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
Project stage: Other
ML20236H9721987-07-31031 July 1987
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
Project stage: Other
ML20237H2081987-08-10010 August 1987
Rev 0 to 01-0300-1629, Independent QA Audit & Technical Quality Review of Trojan Nuclear Power Plant Pipe Support Verification Program
Project stage: Other
ML20237H1881987-08-18018 August 1987
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
Project stage: Other
ML20237G6261987-08-21021 August 1987
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
Project stage: Other
ML20238C6691987-09-0404 September 1987
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
Project stage: Other
ML20235G8061987-09-25025 September 1987
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl
Project stage: Meeting
ML20235Q8051987-09-30030 September 1987
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
Project stage: Other
ML20236A8971987-10-13013 October 1987
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
Project stage: Approval
1987-07-09
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OCT 131987 Docket No.:
50-344 DISTRIBUTION
- Docket FTYe~
EJordan Mr. David W. Cockfield NRC & L PDRs JPartlow Vice President, Nuclear PD#5 Plant ACRS (10)
Portland General Electric Company GHolahan 121 S. W. Salmon Street JLee Portland, Oregon 97204 TChan OGC-Beth
Dear Mr. Cockfield:
SUBJECT:
PIPE SUPPORT DESIGN VERIFICATION (TAC N0. 65726)
In our letter.to you dated August 21, 1987, we concluded that concerns relating to the pipe support design verification, and proposed long-term program for the Trojan Nuclear Plant had been adequately addressed to permit the resumption of power operation. Our letter further stated that a detailed discussion of our review would be provided to you.in a future Safety Evaluation (SE).
Enclosed is the staff's Safety Evaluation.
Issues and details of the Pipe Support Design Verification Long-Term Plan as discussed in your September 30, 1987 letter, will be addressed in future correspondence.
Sincerely, Onginal signed Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation l
Enclosure:
i As stated l
cc: See next page l
V DRSP/PDV
- /D:PDV Tchan:cd mighton 10//J /87 10/)/87 8710230221 871013 PDR ADOCK 05000344 P
PDR
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I'.
t Mr'.: David W.L Cockfield Portland General Electric Company Trojan Nuclear Plant CC: '.
n.
Senior Resident. Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier',' Oregon 97048 Michael J. Sykes, Chaiman.
Board of-County Commissioners Columbia County St. Helens, Oregon 97501
'Mr. David Kish Oregon Department of Energy l
Labor and Industries Building Room 111 Salem, Oregon 97310
' Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria-Lane, Suite 210 Walnut Creek, California 94596 l
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