Letter Sequence Other |
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Results
Other: ML20151L878, ML20215B790, ML20215B804, ML20215G101, ML20215G650, ML20215G653, ML20234D077, ML20236D570, ML20236F145, ML20236F153, ML20236F168, ML20236M855, ML20236M871, ML20237J052
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MONTHYEARML20215G6531987-06-11011 June 1987
Trojan Nuclear Plant Evaluation of Main Feed Line Seismic Restraint Failure
Project stage: Other
ML20215B7901987-06-11011 June 1987
Forwards Evaluation Rept of Main Steam Pipe Wall Thickness, Describing Fatigue & Finite Element Analyses Performed on Affected Piping,Per ASME Boiler & Pressure Vessel Code.Affected Piping Will Be Reexamined in 1988
Project stage: Other
ML20215G1011987-06-12012 June 1987
Forwards Evaluation of Displacement at Main Feedwater Restraint SR4 in Trojan Nuclear Plant & Trojan Nuclear Plant Evaluation of Main Feed Line Seismic Restraint Failure, as Result of Failure During 1987 Refueling Outage
Project stage: Other
ML20215G6501987-06-30030 June 1987
Evaluation of Displacement at Main Feedwater Restraint SR4 in Trojan Nuclear Plant
Project stage: Other
ML20234D0771987-06-30030 June 1987
Advises That Util Agrees to Complete One of Three Listed Actions Re Resolution of Main Steam Line Wall Thickness Issue Before Startup from 1989 Refueling Outage
Project stage: Other
ML20215B8041987-06-30030 June 1987
Evaluation Rept of Trojan Nuclear Plant Main Steam Pipe Wall Thickness
Project stage: Other
ML20236F1531987-07-17017 July 1987
Final Rept Trojan Nuclear Plant SR8 Failure Root Cause Evaluation Steam Condensation-Induced Water Hammer
Project stage: Other
ML20236F1451987-07-27027 July 1987
Forwards Bechtel Western Power Corp Final Rept, Trojan Nuclear Plant SR8 Failure Root Cause Evaluation Steam Condensation-Induced Water Hammer & Impell Corp Summary Rept, Independent Review of Action Plan Items..
Project stage: Other
IR 05000344/19870261987-07-27027 July 1987
Insp Rept 50-344/87-26 on 870706-10.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,External & Internal Exposure Control, Control of Radioactive Matls & Contamination & ALARA
Project stage: Request
ML20236D5701987-07-27027 July 1987
Advises That Util Plans to Resolve Issue Re Code Acceptability Applications Prior to 871201.Util Will Perform Necessary Design & Order Matls to Repair or Replace Unacceptable Main Steam Line Wall Thickness Areas
Project stage: Other
ML20236L3451987-07-30030 July 1987
Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl
Project stage: Meeting
ML20236F1681987-07-31031 July 1987
Rev 1 to Summary Rept, Independent Review of Action Plan Items to Resolve Trojan Main Feedwater Piping Restraint Failure Issue
Project stage: Other
ML20237J0521987-08-21021 August 1987
Responds to Util Proposing to Resolve Issue Re Main Steam Line Wall Thicknesses Which Did Not Meet Min Requirements.Util Adequately Demonstrated That Safe Operation of Plant Until May 1989 Will Not Be Compromised
Project stage: Other
ML20237J2151987-08-21021 August 1987
Advises That Technical Issues Re Accumulator Fill Line Failure & Main Feedwater Pipe Restraint Failure Adequately Addressed by Licensee.Summary of 870617 Meeting Encl.W/O Encl
Project stage: Meeting
ML20236M8711987-11-11011 November 1987
SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures
Project stage: Other
ML20236M8551987-11-11011 November 1987
SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure
Project stage: Other
ML20236M8371987-11-11011 November 1987
Forwards SERs Re Main Feedwater Line Restraint Failure & Accumulator Fill Line Failures at Plant.Repairs Proposed by Util Acceptable to Ensure Integrity of Damaged Sys for Continuing Plant Operation
Project stage: Approval
ML20151L8781988-04-15015 April 1988
Forwards Addl Info Re Six Open Items/Recommendations Noted in NRC 871111 Safety Evaluation of Failure of Main Feedwater Sys Restraint SR-8,per Commitment During Audit of long-term Pipe Support Design Verification Program in Jan 1988
Project stage: Other
1987-07-17
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David W. Cockfield < Vice President, Nuclear July 27, 1987 i
Trojan Nuclear Plant Docket 50-344 License NPF-1 I
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington DC 20555
Dear Sir:
Main Feedwater Restraint Failure Engineering Analyses On June 16, 1987,- the Portland General Electric Company (PGE) report describing the evaluation and root cause of the failure of Seismic Restraint SR-8-.on the Main Feedwater System was submitted to the Nuclear Regulatory Commission (NRC) for review.
This report concluded the cause j
of the damage was water hammer due to steam bubble' condensation. At that time, PGE indicated analyses were being performed confirming this conclu-sion and that a third party review of these analyses was in progress. The report on the steam condensation-induced water hammer analysis is provided as Attachment A.
The third party review is also complete and the report is provided as Attachment B.
This report contains several recommendations regarding the analyses performed, the as-built documentation for SR-8, and the potential need for additional analyses. After reviewing these recommendations and discussing the same with the Architect-Engineer, PGE has concluded the recommendations do not impact the results or conclusions of the review of this issue. The recommendations will be resolved following Plant start-up.
PGE's responses to each of the recommendations are provided as Attachment C.
On June 16, 1987, PCE made a presentation to the NRC on the feedwater restraint issue. During the meeting, a question was raised regarding the adequacy of the concrete to which SR-8 was anchored. PGE has reviewed construction records and the 90 day concrete test cylinders for this con-crete had an average compressive strength of 6142.5 psi. Additionally, from the inspections performed, there was to evidence of a cold joint in j
the concrete nor is one indicated on the drawings. -Therefore, the con-crete is adequate and did not cause pre nature failure of SR-8.
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121 S.W Sdmon Sueet Portiand. Orogon 97204 l,
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Portland General ElechicCorway Decument Control Desk July 27, 1987 Page 2 PCE considers the issue regarding the cause of the failure of SR-8 to be l
closed. As discussed in earlier correspondence, a monitoring program will be conducted to better enable evaluation of dynamic events in the feedwater system and to confirm the adequacy of the design load for SR-8.
Sincerely, Attachments c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Rob Barr NRC Resident Inspector Trojan Nuclear Plant Mr. Davi2 Kish, Acting Director State of Oregon Department of Energy i
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