ML19347F820
| ML19347F820 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 12/31/1980 |
| From: | Draper E GULF STATES UTILITIES CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, RBG-9403, NUDOCS 8105260396 | |
| Download: ML19347F820 (1) | |
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GULF STATES UTILITIES COMPANY ~
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- BEAUMONT. TEXAS 77704 AREA CooE 713 838-3843 December 31, 1980 RBG - 9403 File Nos. G9.5; G9.25.1.1 Oh(p c)
Mr. Karl V. Seyfrit, Director U.S. Nuclear Regulatory Commission
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Region IV Office of Inspection & Enforcement gg21981>h
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Dear Mr. Seyfrit:
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4 River Bend Station - Unit 1 g
Docket No. 50-458 This letter serves as an interim report as comitted to you in our letter of September 12, 1980, regarding the potential 10CFR50.55(e) deficiency concerning an incorrect input to the calculations used to generate Amplified Response Spectra (ARS) for the reactor building structures.
Our A/E (Stone & Webster) has informed us that the error found in the input to the finite element model has been corrected and that the first Safety / Relief Valve (SRV) case (i.e., all 16 valves) has been rerun. The ARS plots are being generated at this time. Preliminary results for the "all valve case" indicate that the acceleration values are generally less than those originally calculated. Other SRV and LOCA load cases are to be run and new ARS's are to be generated.
Final analysis of all the cases is currently on a schedule to meet our comit-ment of April 1, 1981, as stated in our Septamber 12, 1980 letter mentioned above.
Sincerely,
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E. Linn Draper, Vice President Nuclear Technology WJR/te god Si 0 T/052603%
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