ML20008F695

Final Deficiency Rept Re Incorrect Input to Finite Element Model Used to Calculate Amplified Floor Response Spectra of Reactor Bldg,Initially Reported on 800912.Concludes Condition Not Reportable Per 10CFR50.55e

ML20008F695
Person / Time
Site:	River Bend
Issue date:	04/01/1981
From:	Draper E GULF STATES UTILITIES CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, RBG-10-034, NUDOCS 8104210509
Download: ML20008F695 (1)

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4 , t f GULF STATES UTILITIES COMPANY "

• *, 3 ? 08760ESOX 275' . a SEAVMONT TEXAS ??*04 AREA OOCE 713 939 6631 April 1, 1981 RBG- 10,034 Files G9.5, G9.25.1.1 9 g g\\',j! -

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! b Mr. Karl V. Seyfrit, Director #

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U.S. Nuclear Regulatory Commission Region IV C[ $N [g ,

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Office of Inspection & Enforcement \,

611 Ryan Plaza Dr. - Suite 1000 \- 9# .

Arlington, TX 76011

Dear Mr. Seyfrit:

4- o\j River Bend Stas.~on Unit 1 Docket No. 458 Gulf States Utilities Company has completed our evaluation con-cerning an incorrect input to the finite element model used to calculate the amplified floor response spectra (ARS) of t!.e reactor building structures due to the hydrodynamic forces in the suppression pool.

This subject was verbally reported to your staff on Augast 14, 1980 as a potential 10CFR 50.55(e) deficiency and formally reported to you in our letter of September 12, 1980.

Our A/E (Stone & Webster) has determined that by correcting the discrepancy of the input in the calculations used for the ARS has not resulted in an adverse impact on the design of the piping system, equipment and structual steel floors. Had this problem remained uncorrected, it would not have affected the safety of the plant.

! Therefore, we have determined that the problem is not a reportable deficiency under 10CFR 50.55(e).

I This completes the 10CFR 50.55(e) evaluation requirement. It i is concluded that no reportable deficiency exists.

Sincerely,

b. L

E. L. Draper, Jr.

Vice President - Nuclear Technology l

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8104210507 -

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