Letter Sequence Meeting |
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Results
Other: ML20151L878, ML20215B790, ML20215B804, ML20215G101, ML20215G650, ML20215G653, ML20234D077, ML20236D570, ML20236F145, ML20236F153, ML20236F168, ML20236M855, ML20236M871, ML20237J052
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MONTHYEARML20236X2381987-06-0404 June 1987
Kerotest Valve Flow Test, Subtask Rept,Accumulator Fill Line Failure.Chronology & Action Plan Encl
Project stage: Other
ML20215G6531987-06-11011 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
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
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
ML20238C3451987-09-0404 September 1987
Forwards Response to NRC Request for Addl Info Re Accumulator Fill Line Nozzle Stress Calculation.Areas Discussed Include Estimate of Previous Nozzle Loading & Fatigue Usage Factors
Project stage: Request
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
ML20236X2261987-12-0303 December 1987
Forwards Presentation Handout & Subtask Rept Describing Backflow Test Conducted to Verify Postulated Failure Mode of Accumulator Fill Line & Recovery Action Plan
Project stage: Other
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
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Docket No. 50-344 1 1937 MEMORANDUM FOR: Dennis F. Kirsch, Director Division of Reactor Safety and Projects Region V FROM:
George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
SUBJECT:
TROJAN STARTUP ISSUES (TAC N05. 65471, 65472 AND 65473)
By your memorandum to G. Holahan dated June 3,1987, Region V requested that NRR review certain licensee analyses associated with the Portland General Electric Company's (PGE) evaluation of the Trojan accumulator fill line failure, main feedwater pipe restraint failure, and the main steam line wall thickness issue. The specific analyses requested for review were identified in the Enclosure to your memorandum.
NRR has com31eted its initial review of the specified analyses, and generally concludes t1at the technical issues related to the accumulator fill line failure, and the main feedwater pipe restraint failure have been adequately addressed by the licensee in their respective June 12, 1987, and followup submittals. The evaluations appear to have been sufficiently thorough and comprehensive to justify resumption of power operation following their 1987 refueling outage. The enclosed meeting summary (dated July 30, 1987) of the NRR/PGE June 16, 1987 meeting regarding the same subjects also provided a basis for our determination. A more detailed discussion of our review will be provided in our Safety Evaluation to the licensee.
We have also review the licensee's June 11, 1987 evaluation related to the main steam line wall thickness issue. As stated in our enclosed meeting summary, we do not agree with the licensee's assertion that the use of more rigorous analytic techniques and higher allowable stresces as permitted by ASME III Section NB3600, by themselves, demonstrates equivalent conformance to ANSI B31.7 Class 2.
Given the fact that this application of the Code requirements is a point of interpretation, PGE proposed by letter dated July 27, 1987, that the issue be resolved by one of the following ways:
(1) staff concurrence of the licensee'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. The licensee also provided their justification for operating in the interim period given the current measured pipe wall thicknesses.
h[bbob b P
Dennis F. Kirsch 2-We have reviewed PGE's July 27, 1987 proposal and justification, and find.them 4
to be acceptable. PGE adequately demonstrated that safe operation of the plant I
until May 1989, with the given main steam line wall thickness configuration, J
will not be compromised. A detailed discussion of our review will be provided in our Safety Evaluation to the licensee.
' Driginal signid by:
Cecrge W.10tighlan George W. Knighton, Director 3
Project Directorate V.
l Division of Reactor Projects
- III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
i As stated i
T. Chan NRR/PD5 l
Ext. 28997 DISTRIBUTION:
1 Docket: File s NRC & Local PDR l
PD5 Memo DCrutchfield j
TChan i
JLee LMarsh GWKnighton GHolahan 0GC-Bethesda EJordan JPartlow ACRS(10) l
- EMEB DR dg.PD5 JLee TChan LMarsh G
ton 08/20/87' 08/20/87 08/20/87 08/jf/87 1
i
