Letter Sequence Approval |
|---|
|
Results
Other: ML20151L878, ML20215B790, ML20215B804, ML20215G101, ML20215G650, ML20215G653, ML20234D077, ML20236D570, ML20236F145, ML20236F153, ML20236F168, ML20236M855, ML20236M871, ML20237J052
|
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
p u
,l q w 4'.
,o 4,
ms y
t, g,
/
--.c y,,
~
sf o
4 November 11,(1987J
- r.,
3 6
- i-
'j Docket No. 50-344 nD y"'
4 1
s 11
.u
'TChan.
'i NRC-& Local PDRs' (OGC-Bethesda' Mr. David W. Cockfield.
.PDS Readingi
?EJordan Vice President, Nuclear-DCrutchfield' JPartlow Portland.GenerallElectric Company GHolahan.
.JLee-121 S.W.. Salmon: Street a
l Portland,. Oregon 97204
Dear'MrFCockfield:
SUBJECT:
MAIN FEEDWATER LINE RESTRAINT FAILURE lAND ACCUMULATOR FILL LINE FAILURES-TROJAN f"JCLEAR PLANT.(TAC NOS; 65471/ AND 65473) y; L
As _a result of two accumulator fill line failures, anddhe. identification of a' main feedwater line restraint _ failure during the 1987) refueling-outage, the j-
..y
+
L NRC's Region-V office requested that the Office of Nuclear R,eactor Regulation..
<l
.(NRR)LreviewcertainanalysesassociatbdLwithPortlandGent.ralLElectricCompany's i
(PGE) evaluation of the above. identified-issues. 'These analyses were submittedj to.the. staff by two PGE letters dated June 12.11987.
L A June 116,.1987 meeting between PGE and NRR (as documented in the staff's.
l~
July 30,'1987 Neeting Summary) resulted in the staff's preliminary conclusion that the two issues had been adequately addresssed.
~ '
}y
(
.We have completed out. detailed review of the PGE analyses and proposed correct-1 ive actions. Our review concludes that PGE has identified the causes of both d
l events and has taken appropriate actions to prevent their< recurrences. LThe
.t repairs proposed by~PGE.are acceptable to. ensure inte0rity of the damaged systems, Jl for continuing plant. operation.
4 Our Safety Evaluations are enclosed.
In certain subject areas, a confirmation or verification of fact has been requested. For these' areas, we ask that you notify us of the results upon completion of your action.
Sincereiy, I
n Terence L. Chan', Project Manager c
q Project Directorate V;.
Division of Reactor Projects III,;
j J
IV, V and Special Projects'.
~
]
Office of Nuclear Reactor-Regulation' i
'n
Enclosure:
0 As stated j
,cc:.. See t page-h
- DRSP/PD -
DRSP/D:PDS.
i lTChan GWKnighton 8711130306 871111 c
/// $/87 -
((/j/87:
I PDR DR ADOCK 05000344 R: '
}
1 x
w m
'a a.
z
p, 1
.,l 3
i Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plarit cc:
Senior Resident Inspector.
U.S. Nuclear Regulatory Comission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Michael J. Sykes, Chairman 1
Board of County Commissioners Columbia County St. Helens, Oregon 97501' i
Mr. David.Kish Oregon Department of Energy.
c Labor and Industr.ies Building
'j Room 111 i
Salem, Oregon 97310 1
Regional Administrator, Region'V U.S. Nuclear' Regulatory Commission 1
1450 Maria Lane, Suite 210 J
Walnut Creek, California 94596
/
i j
j q
m
.g
