ML19225C762

Forwards Corrected Copy of IE Bulletin 79-14,Revision 1, Seismic Analysis for As-Built Safety-Related Piping Sys

ML19225C762
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/19/1979
From:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Goodwin C PORTLAND GENERAL ELECTRIC CO.
References
TAC-12369, NUDOCS 7908020407
Download: ML19225C762 (1)

Text

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g ft,vi.p 9 f SUIT E 232, WALNUT CR E E K PL AZ A S'e,v,,e' V. ALNUT CR EE K. C Alt FOR NI A 94596 July 19,1979 Docket No. 50-34; Portland General Electric Cenpany 121 S. W. Salmon Street Portland, Oregon 97204 Attention:

Mr. Charles Goodwin Assistant Vice President Gentlemen:

Attached is a corrected copy of Revision 1 to IE Bulletin No. 79-14 mailed to you cn July 18, 1979.

A sentence was inadvertently caitted from the previous copy.

Sincerely,

,I/

,d3 R. H Engelken Director

Enclosure:

IE Sulletin No. 79-14, Revisicn 1 - Correcced Copy cc w/ enclosure:

3. Wichers, PGE F. C. Gaidos, PGE

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IE Bulletin No. 79-14 July 18,1979 Revision 1 Page 2 of 3 Acticn to be taken by Licensees and perait Holders:

All power reactor facility licensees and ccnstruction permit hciders are requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actual configura-tico of safety-related piping systema. The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Classification" Revision 1, dated August 1,1973 cr as defined in the applicable FSAR.

The action items that follow acoly to all safety related pioina 21/?-inches in ciameter and greater and to seismic Catecory I cioing,_

regarcless of size wnica was dynamically analyzec by coccuter. For older plants, wnere Seismic C?.tegory I requirements did nct exist at the time of licensing, it must be shcwn that the actual configuraticn of frejd safety-related systems, utilizing oicing 71/2 inches in diameter and greater, meets design requirements.

Specifically, each licensee is requested to:

1.

Identify inspection elements to be used in verifying that the seismic analysis input information conforms to the actual ccnfiguration of safety-related systems.

For each safety-related system, submit a list of design documents, including title, identification number, revision, and date, which were sources of input information for the seismic analyses. Also submi a description cf the seismic analysis input information which is contained ia each document.

Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3. Submit all of this infccmation within 30 days of the date of this bulletin.

2.

For pcrtions of systems which are normally accessible *, inspect one systen in each set of redundant systems and all noiredundant systems for con-forcance to the seismic enalysis input infccmation set forth in design cccuments.

Include in the inspection: pi, e run gecmetry; supcort and restraint cesign, lccacions, function and clearance (inclucing ficer and aall ;enetraticn), embecments (excluding those ccvereu in IE Eulletin 79-C2); pipe attachement3; and valve and valve operator lccaticns and weights (excluding tncse ccvared in ;E Bulletin 79-04).

Wi:nin E0 cays of the date cf this bulletin, submit a descripticn cf the results cf this inscecticn. Where ncnconformances are found which affect cperability of any systen, the licensee will expedite completion 0 ^ tne inspecti:n described in Item 3.

' Norm. y accessible rer.ers to t.ncse areas of the plant which can <e entered during reactor.peraticn.

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