ML19241B439

Forwards LER 79-019/01T-0

ML19241B439
Person / Time
Site:	Peach Bottom
Issue date:	07/06/1979
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19241B440	List: ML19241B439 ML19268A258
References
NUDOCS 7907170157
Download: ML19241B439 (2)

Text

. abs PHILAD ELPHI A ELECTRIC COM PANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 12151041 4000 July 6, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Ragulatary Commission 631 Park Avenue King SF Prussia, Pennsylvania 19406

SUBJECT:

Licensee Event Reoort Narrative Description The following occurrence was reported to Mr. Greenman, Region I, Office of Inspection and Enforcement on June 21, 1979.

Reference:

Docket Number 50-278 Report No: LER 3-79-19/1T Report Date: July 6, 1979 Occurrence Date: June 21, 1979 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, PA 17314 Technical Specification

Reference:

Technical Specification 6.9.2.s(9) requires reporting

'p erf ormaace or structures, systems, or components that require remedi:1 action or corrective measures t o p revent operation in a manner less conservative than assumed in the accident analysis it the safety analysis r e p o r t . . .

Description o_f, t h e Event:

As part of the seismic support inspection program initiated by IE Bulletin 79-02, an anchor associated with the RCIC piping was found to have two b olts which could not be properly torqued.

An engineering analysis was performed and a determination made that, in the as found condition, the anchor would not be capable of withstanding a combination of operating and seismic loads without overstressing the anchor bolts.

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M Mr. Boyce 11 . Grier Page 2 July 6, 1979 LER 3-79-19/IT Following the identification of the two loose concrete inserts, Bechtel Power Corporation analyzed this support in order to determine its load carrying capability. This analysis concluded that, with all six bolts in place two bolts have a safety factor of 1.8, two bolcs have a safety factor of 3.6, and the remaining two bolts have a safety factor in excess of 5 based on manufacturer's published ultimate load.

Consequences 31 Event:

The remainder of the RCIC anchors have been found to be acceptable. The as inatalled anchor plate does have sufficient load carrying capacity with all components properly installed to withstand the operating and seismic loads applied. The safety significance is minimal, due to the low probability of a acasmis event. HPCI would be available during and after a seismic event.

Cause of Event:

The cause of this occurrenc' was the improper installation of the anchor bolts.

Corrective Action:

The two imp r;p e rly installed shell type anchor bolts have been removed and replaced with wedge type anchor bolts. This returned the support to its original design capability. An additional sucport strut has been added to increase the load carrying capability of this support and attain a uinimum anch r bolt safety factor of 5.

Yours truly,

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l l&,h*r DL' y <

M. J. Co>ney /

uperintendent 4eneration Division-Nuclear Attachment cc: Director, NRC - Office of Inspection and Enforcement Mr. Norman M. Maller, NRC - Office of Management &

Program Analysis 46i 2/8