ML20237J215

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

ML20237J215
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/21/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
TAC-65471, TAC-65472, TAC-65473, NUDOCS 8708260069
Download: ML20237J215 (2)

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.

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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 .

' 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

• See previous concurrence

• DRSP/PD5 *DRSP/PDS *EMEB DR JLee TChan LMarsh G dg.PD5 ton 08/20/87' 08/20/87 08/20/87 08/jf/87 1

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