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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Text
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1 1
ammme Pbetlanci General Electric Coirvisiy mm.
~
David W. Cockfield Vice President, Nuclear i
July 27, 1987 j
i Trojan Nucle.ar Plant Docket 50-344 License NPF.-l U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington DC 20555
Dear Sir:
Main Steam Line Wall Thickness As a result of main steam piping wall thickness measurements obtained during the 1987 refueling outage, analyses were performed to demonstrate the acceptability of the as-found conditions. The analyses were submitted to the Nuclear Regulat ry Regulatory Commission (NRC) on June 11, 1987.
Subsequently, Portit..., Cencral Electric Company (PGE) representatives met with the NRC staff and participated in several telephone conversations concerning this subject. Our letter of June 30, 1987 provided additional information in support of the analyses submitted on June 11, in support of Code application and acceptability, and proposed actions to be accomplished over'a two-year period.
The analyses submitted on June 11, 1987 showed that operation could continue for an indefinite period of time.
In subsequent telephone conversations with the NRC staff, PGE indicated a minimum of 18 months was necessary to order materials and perform the necessary design in order to replace those portions of piping below minimum ullowabic thickness should this action be required. In addition, PGE had proposed an additional six months in which efforts would be made to demonstrate the acceptability of the code applications used for the main steam line analyses submitted on Juno 11.
From those time periods, the acceptability for operation for two years was deduced.
h j
Mdj P
l1 ik, 121 S.W Satmon Street. Port!ard Oregon 97204
POfUallCIGiOt10fal MCOnWiiiOY U.S. Nuclear Regulatory Commission j
July 27, 1987 Page 2 PGE proposes to resolve this issue regarding code acceptability applica-tions prior to December 1,1987.
If determined necessary, PCE will perform j
the necessary design and order materials to repair or replace the affected area of the steam lines prior to the startup from the refueling outage in 1989. We trust this approach and schedule is acceptable to the NRC staff.
Sincerely, c: John B. Martin Regional Administrator, Region V
-U.S. Nuclear Regulatory Commission Mr. David Kish, Director State of Oregon Department of Energy Mr. R. C. Bare NRC Resident Inspector Trojan Nuclear Plant
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