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Forwards Stiffness Values of Supporting Concrete of RCS Equipment Supports for Verification Analyses of Dynamic Asymmetric Loads on Supports,In Response to SB Burwell & Rk Mattu 791017 Requests
	ML19210D586
Person / Time
Site:	Comanche Peak
Issue date:	11/20/1979
From:	Rock H; GIBBS & HILL, INC. (SUBS. OF DRAVO CORP.)
To:	Merritt J; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
References
	GTN-41826, NUDOCS 7911270351
	Download: ML19210D586 (10)
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Gibbs S HillInc.

E NGIN E E R S DESIGNERS CONSTRUCTORS oiRECT DIAL E XT E N SIO N

<2isi Teo. 4 4 5 0 November 20, 1979 GTN-418'26 Texas Utilities Generating Company Post Office Box 1002 Glen Rose, Texas 76043 Attention:

Mr. J. T. Merritt Manager of Construction and Engineering Gentlemen:

TEXAS UTILITIES GENERATING COMPANY COMANCHE PEAK STEAM ELECTRIC STATION 1981 2300 MW INSTALLATION G&H PROJECT NO. 2323 STAFF ANALYSES OF DYNAMIC ASYMMETRIC LOADS ON PRIMARY COOLANT SYSTEM SUPPORTS In accordance with the request of Messrs.

S.

B.

Burwell and R.

K. Mattu of the NRC at a meeting of October 17, 1979 at the Comanche Peak Site, Glen Rose, Texas, Gibbs & Hill is for';arding a copy of the following additional for the subject verification analyses: stiffness values of supporting concrete for the RCS equipment supports.

This information is given in the form of figures 1 to 4, Tables 1 to 4 and a microfilm of a computer printout.

The supporting points of the RCS are separated into three groups according to the nature of the supports and their relative loca-tions within the reactor building.

The stif.fness of one grcup is considered to have only a small effect on the o,ther and there-fore is separable.

The three groups are as follows:

1.

Steam generator lateral supports (8 points) 2.

Reactor coolant pump and cross-over leg lateral restraints (4 points) 3.

RCS vertical supports (9 points) 6M s i 1397 167 393 SEVENTH AV E N U E NEW YOR K, N. Y.10 0 01 CASLE: GIBOSHILL NEW YORK 7911270h

a GTN-41826 November 20, 1979 Texas Utilities Generating Company The corresponding supporting points are shown on Figures 1 through 3.

The stiffness matrices of these groups are presented in the form of a computer printout.

Six degrees of freedom (DOF) is global coordinates are considered for each support node.

Thus the size of the matrices are 48 X 48, 24 X 24 and 54 X 54 respectively.

Tables 1 through 3 show the DOF versus nodal directions.

Because of symmetry, only the upper triangular matrix is given in the printou t.

The units are pounds, radians and feet.

The matrices are given by row in the format of (2I5, SE14.5) with the first integer representing the row number of a matrix and the second the sequence of cards in a row.

The flexibility matrices, obtained by inverting the stiffness matrices, are also given for the upper triangular portion in the same way as the stiffness matrices.

The stiffness matrix (30 X 30) and the corresponding flexibility matrix for tha pressurizer supports (see Figure 4) are also given in the print-out.

'Zae DOF versus nodal directions for the pressurizer supports are tabulated in Table 4.

Mr. Thimmes, of your office, also asked for verification of the gap dimension between the Steam Generator and the Upper lateral support beam, G&H drawing 1457F34. The dimension is 1/32" in hot position all around.

If we can provide any additional information or clarification, please call R. E.

Ballard at 212-760-4438.

Very truly yours, GIBBS & HILL, INC.

Harvey R.

Rock HRR/REBa:mml Manager of Projects lL cc:

ARMS (B&R SITE) Orig. L H. C. Schmidt (TUSI DALLAS) 2L l A R.

E. Heim (G&H SITE) lL P. VandeVisse (TUSI SITE) lL, lA S.

B.

Burnwell (LIGHT WATER REACTORS BRANCH NO.

2, Nuclear Regulatory Commission, Washington D.C.

20555) lL,lA B. F.

Saffell, Jr. (EG&G IDAHO, INC. P. O. Box 1625, Idaho Falls, ID 83401) lL, lA, 1 Microfilm

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