ML20003A377

Interim Deficiency Rept,Originally Reported on 801217,re Structural Design Deficiency in Reactor & Auxiliary Bldgs. As-built Bracket Stiffener Plates Must Be Modified to Satisfy Design Criteria.Will Submit Final Rept by 810831

ML20003A377
Person / Time
Site:	Hope Creek, 05000355
Issue date:	01/14/1981
From:	Martin T Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8102030577
Download: ML20003A377 (2)

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Thomas J. Martin Public Service Electric and Gas Company 60 Park Plaza Newark NJ.07101 201/4304316 vice pres.o.nt eng.n.em and constructi " January 14, 1981 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office Of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

STRUCTURAL DESIGN DEFICIENCY NO. 1 AND 2 UNITS (50-354/355)

HOPE CREEK GENERATING STATION On December 17, 1980, a verbal report was made to Region 1, Office of Inspection and Enforcement representative, Mr. J.

Mattia, advising of a potential significant item. The following information is submitted as required by 10CFR50.55(e).

1. Description of the deficiency:

During our Architect Engineer's review of all structural members for adequacy after actual equipment and piping loads are fully established, and as mandated by their general civil-structural design criteria, they concluded ,

that several as-built bracket stiffener plates must be

' modified to satisfy existing design criteria.

This situation was discovered during the review of the j

slab supports for elevation 102' in the Unit #1 Reactor Building. Investigation has shown the problem exists in both the Unit #1 and Unit $2 Reactor Buildings, and in the Auxiliary Building.

The design method used was one presented in general civil-structural design criteria and was also as deline-ated in the American Institute of Steel Construction (AISC), " Specification for the Design, Fabrication and l

Erection of Structural Steel for Buildings", dated February 12, 1969, with Supplement No. 1 of November 1, 1970, Supplement No. 2 of December 8, 1971, and Supple-f0/

3 ment No. 3 of June 12, 1974. The cause of the design /

l problem was that although shear and compressive forces //O were considered, the ef fect of bending on bracket stiffener plates caused by load eccentricity was not considered.

810:.o $l7 s m y e <wy.

= v-e

o Mr. Boyce H. Grier 1/14/81

2. Analysis of safety implications:

An analysis of safety implications will be conducted following completion of a case-by-case review of all questionable beam seats which have already been installed.

3. Corrective Action:

Our A/E will determine and issta appropriate design, requirements for construction. This work is presently in progress and will be completed by August 13, 1981.

This will involve obtaining as-built data, preparing case-by-case repair requirements, and revising design requirements for beam seats to be constructed in the future.

Upon completion of the review of each suspect beam seat and analysis of the data concerning required repairs, we will submit a final report to ti.2 NRC. We expect. to issue this report on or about August 31, 1981.

Very truly yours, CC: Office of Inspection & Enforcement Division of Reactor Construction Inspection Washington, D. C.

BH14/1 1/2

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