Letter Sequence Other |
|---|
|
|
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
[Table View] |
Text
.
l AUG 211967 Docket No.:
50-344 DISTRIBUTION
- Docket File"r EJordan NRC & Local PDRs JPartlow Mr. David W. Cockfield PD#5 Plant File ACRS (10)
Vice President, Nuclear GHolahan LMarsh Portland General Electric Company JLee RStarostecki 121 S. W. Salmon Street TChan DCrutchfield Portland, Oregon 97204 OGC-Bethesda
Dear Mr. Cockfield:
SUBJECT:
PIPE SUPPORT DESIGN VERIFICATION (TAC N0. 65726)
Due to concerns regarding the design adequacy of certain pipe supports at the j
Trojan Nuclear Plant, the NRC, pursuant to 10 CFR 50.54(f), requested l
information to assess safe operation of Trojan following its 1987 refueling cutage, by letter dated July 9, 1987.
Portland General Electric Company (PGE) provided information in response to j
the staff's request in a July 10, 1987 letter, and during a July 16, 1987 meeting. Additional concerns were expressed following a July 21-23, 1987 NRC audit of the support verification effort, at the Bechtel - San Francisco l
offices. Responses to these concerns were addressed in PGE letters dated July 27
)
and July 31, 1987, and August 18, 1987, and during a August 20, 1987 meeting.
J Based on the information provided, we find that PGE has adequately evaluated the design adequacy of those pipe supports which were part of the original support design verification program, and that these supports will fulfill the requirements under which Trojan was licensed, as stated in Trojan's Updated Final Safety Analysis Report. We also find your proposed long-term program, which will include the evaluation of the adequacy of current and past Architect-Engineer's design activities to have been adequately addressed.
Details of the long-term program were committed to be provided to the staff for approval by September 30, 1987.
As such, we conclude that power operation may be resumed. A detailed discussion of our review will be provided to you in a forthcoming Safety Evaluation.
Sincerely, p l ggnsd by l
8709020338 870021 Dennis M. Crutchfield, Director PDR ADOCK 0500 4
Division of Reactor Projects - III, I
P IV, V and Special Projects Office of Nuclear Peactor Regulation cc: See next page
- See previnus concurrence i
DRSP/PDV
- DRSP/AD JLee TChan:cd LMarsh GWKnf Mn GHolahan 8/ /87 8/21/87 8/21/87 8/21/87 8/21f 8/21/87
- NRR/ADT DCrutchfield RStarostecki 8/21/87 8/21/07 i
Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant cc:
Senior Resident Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. David Kish Oregon Department of Energy 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
.__
