ML19276H412
| ML19276H412 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/24/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19276H411 | List: |
| References | |
| NUDOCS 7910220228 | |
| Download: ML19276H412 (2) | |
Text
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'o, UNITED STATES I 'f ) 3 4{" j' NUCLEAR REGULATORY COMMISSION s,.l,- h'T,"y[/. [<
REGION V C, fdEg 1990 N. CAllFORNI A DCULf VARD
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U SUITE 202. WALNUT CREE K PLAZ A c
WALNUT CREEK, CALIFORN!A 9459G August 20, 1979 Docket ;io.79-344
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Portland General Electric Ccmpany 121 S. W. Salmon Street Portland, Oregcn 97204 Attention:
Mr. Charles Goodwin Assistant Vice President Gentlemen:
Enclosed is IE Bulletin tio. 79-02, Revision 1, Supplement flo.1, which clarifies fiRC positions en actions requested with regard to your power reacter facility (ies) with an cperating license.
Should you have any questions regarding this Bulletin or the actions required by you,, please contact this office.
Sincerely, b
% c 5-R. H. Engelken Director
Enclosure:
IE Bulletin tio. 79-02 Revision tio. 1 (Supplement tio.1) cc w/ enclosure:
B. Withers, PGE
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August 20, 1979 IE Bulletin t:o. 79-02 Revision fio. 1 (Supplement !!o. 1)
PIPE SUPPORT BASE PLATE DESIG::S USItiG C0!! CRETE EXPA!SIO: A:;CHOR BOLTS Description of Circums'tances:
The supplement to IE Bulletin fio. 79-02 is intended to establish criteria fer the evaluation of interim acceptability of plant operaticn with less than the design factors of safety for pipir.c supports due to as-built probiens, under design, base plate flexibility, or anchor bolt deficiencies.
In the reviews for system cperability of the Duane Arnold and Crystal River facilities, criteria have been developed by the !;RC staff that defines pipe suppor:
operability.
The criteria have been applied in lieu of other analysis or evalua-tion.
Specifically, the licensees identified problems with pipe supports in which the original design factors of safety were not met but some lesser margin was available.
The design margins of four or five are intended to be final design and installation objectives but systems may be classed as operable on an interim basis with sone lesser margin providing a program of restoration to at least the Bulletin factors of safety has been develcped.
Facilities which fall outside the operability criteria are considered to probably require a Technical Specifica-tion exception and will require review on a case by case basis.
. Action to be Taken by Licensees:
For the following two cases, plant operation may continue or may begin:
For the support as a unit, the factor of safety compared to ulti-a.mate strengths is less than the original design but equal to cr greater than two.
b.
For the anchor bolts the factor of safety is equal to or greater than two and for the sucport steel the original design factor of safety com-pared to ulitmate strengtns is met.
The abc ce criteria may be a: plied provided that the affected systems are up-graded to design mar;i.s ci safety expeditiously fcr ncrmally accessibile support
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and by tne next refueling for ncnaccessible supp;rts.
Accessibility is as de-finec in Bulletin ito. 79-14 s.nere "ncrmally accessible" refers to those areas of the olant whicn can be entered during reactor operation.
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IE Bulletin f o. 79-02, Revision flo.1 Page 2 of 2 Supplerent t'o.1 August 20, 1979 1.
Any suppor.t net satistying the criteria should be classed as inoperable and the Technical Specification action statement r.et unless it can be shcun that the system can function in a design basis seisnic ever.t without the support.
2.
Repairs to ' supports should result in return to the design factor of safety.
3.
Operations nay be continued while repairs to upgrade the system frca a factor of safety ecual to or greater than two with rescect to design loads are performed.
Consiceration must be given to the effect of the repair process on support function and system operability.
In other words the time the support is not functional should be limited to T.S. action stacement times or the support must be determined not to cause the system to be unable to perform its function in a seismic event. The licensee should also exercise care not to take several supports on a given systen out of service at the same time or cause both trains of one safeguards systen to be made inoper-able at the same time.
Control over workmen on safety related systens during plant operation requires a high degree of control by the licensee.
4 There are no special reporting requirements for this supplement to the Bulletin; hcwever, the reporting requirements as set forth in the regula-tions and licenses nust be met.
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