TENNESSEE VALLEY AUTWORITY CHATTANOOGA. TENNESSEE 37401

WO0 Chinintat Street TbmmrEI

Novemer 30, 1962

VBD~-50-390/6246 VDID-50-391/82-43

U.S. Nuclear Regulatory Cinaission Region tl Attn: Mr. James P. O'Reilly, Regional Admnistrat.orci 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 C

Dear Mr. O'Reilly:

VATTS BAR NUCLEAR PLAINT UNITS 1 AND 2 - INCORRECT SEISMIC DISFLACNTS AND RESPONSE SPECTRA USE - WBRDý-50-390/82-46g VERD-5O-391/82-43 - THIR INTERIM REPORT

The subject deficiency was initially reported to NRC-OIK Inspector F. Long an April 30, 1982 in accordance with 10 CPU 50.55(e) as NCR VW CEB 8208. Interim reports wer submitted co Jura 1 and August 20, 1962. Enclosed is our third interim report. The scopet of this deficiency has been expanded to include other affected system. The description of condition and title have beon modified appropriately. The submittal date of this report was discussed with Inspector R. V. Crienjak on Novemer 23, 1982. We expect to submit our next report on or about March 23, 1983.

If you have any questions, please get in touch w-.ýth R. R. Shell at F"S 858-2688.

very truly yours,

TENNESSEE VALLEY AUTHORITY

L. NoMla3e Nuclear Licensing

Enclosure cc: Mr. Richard C. DeYcung, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

R212090160 821130 ON ADMK0500039,0

B PDR

An f q, it ofppoo.n.ty f . 6' c.9-

VUlY3 BU N=CLE" PLTUW I = 1 INM 2 BOOM=3E SISIC DM~ACOMS ANM miSOMz SPNCTR M

10 CPR 50.55(e) WN MU CXB 8am

VDU-50-3901'82-U6, UDB-50-39 1/82-43 TH-1IRD Iwr UPUT

Description of Deficiency

In the design review of maini feeduater limes, it us di300vere that some erroneous displacements were used for the steam generator nozzle in main feedwater analysis problem 0600200-02-03- The cause of this deficiency is the oversight by TVA in the coordinate transformation from vendores coordinate system to "ie TVA' s 'enndinaet system. At the sams time it am also discovered that an incorrect seismic response spectra for steem generator No. 1 was used in main feeduater analysisa problem 0600200-02-01. The cause of this second deficiency is still undetermined and is being investigated.

Subsequent investigations have found other safety-related lines attached to the reactor coolant loop which have used uncomservative spectra. These errors can have an adverse effect of Increasing the stress in the piping and in the nozzle. They were recognized for unit 1, but the effect will be considered for both units.* The new probless have been identified on chemical volume control, steem generator blowdown, safety injection, and reactor coolant loop system.

Both problems were reanalyzed to determine the final effect on the piping and the nozzle. A careful review of all the other main feedmuater analysis problems uas done and it uas determined no other displacesmet errors occurred ' In these analyses.

A coordinate system transformation relation uas developed and a data sheet uas filed vith the vendor data as a meane to avoid the potential for human error when transforming coordinates from the vender tn TVA system on main feedwater problems. A now seismic responui spectra was correctly digitized and used in the reanalysis of pr3blem 0600200-02-01.

Both probleme, 0600200-02-01 and 0600200-4 2-03, had similar end resuts. Tnere uas no overstressing of the piping rw' of the nozzle, but some significant changes occurred in the support loads. These loads were reviewed by the design projects personnel and were determined to be acceptable.

TVA is in the process of reanalyzing the new problems on the other safety-related systems.