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
[Table View] |
Text
'
AUG 211987
' Docket No.: 50-344
_ DISTRIBUTION,
4 Docket' File C ACRS(10)
NRC & Local PDRs PD5 Plant File Mr. David W.'Cockfield GHolahan Vice President, Nuclear Tchan Portland General Electric Company JLee 121 S. W. Salmon Street OGC-Bethesda L
. Portland, Oregon 97204' EJordan JPartlow
Dear Mr. Cockfield:
SUBJECT:
TROJAN-MAINSTEAMLINEWALLTHICKNESS(TACNO.65472)
'By letter dated June 11, 1987, Portland General Electric Company (PGE) informed the staff of observed main steam line wall thicknesses which did not meet the specified minimum requirement. The wall thickness discrepancies were confined to areas at the flow-limiting venturi outlet for all steam generators.
The'cause of the discrepancy was attributed to machining of the pipe spools in preparation for installation of the venturi. As a result, PGE provided results of analyses performed in accordance with ASME Section III, NB3600, in order to demonstrate complicace to Trojan's Code of Record for this portion of piping, ANSI B31.7, Class 2.
Since this ap)lication of the Code req'uirements is a point of interpretation, PGE 3roposed )y letter dated July E7. 1987, that this issue be resolved in one of tie following ways:
(1) staff concurrence of PGE's interpretation of the ASME Code by December 1,1987, or (2) the completion of pipe replacement by the end of Trojan's 1989 refueling outage. PGE's justification for interim operation was based upon the results of the June 11, 1987 analyses.
We have reviewed your July 27, 1987 proposal and justification, and find them to be acceptable. PGE has adequately demonstrated that safe operation of the plant until May 1989, with the given main steam line wall thickness configuration, will not be compromised. A detailed discussion of our review will be provided to you in a forthcoming Safety Evaluation.
Sincerely, OrW M'd U Terence L. Cinn, Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects i
Office of Nuclear Reactor Regulation cc: See next page DRSP/PDV DRSP/PDV BC/ FE V DRS l
JLee TChan:cd LMash]. GWK ighton j
8/ /87 8/N/87 8/J{/87 8/// /87 0FFICIAL RECORD COPY 8708250277 870821 PDR ADUCK 05000344 P
PDR
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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 i
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