RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads

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Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads
ML20055D017
Person / Time
Site: River Bend Entergy icon.png
Issue date: 06/26/1990
From: Odell W
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-33120, NUDOCS 9007030089
Download: ML20055D017 (2)


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GULF STATES UTILITIES COMPANY *G 7% tit Bf ND 5.l A flOA POST Of f Kf 80x 2N $1 FRANC $VtLLE, LO3SiAN A 73775 ARLA CODE $04 CM 60S4 346$651 June 26 , 1990 103- 33120 File No. G9.5, G9.42  ;

U. S. Nuclear Regulatory Ccmnission l Docum2nt Control Desk l Washington, D.C. 20555 '

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River Bend Station - Unit 1 '

Docket No. 50-458 On May 14, 1990 Gulf States _ Utilities (GSU) Ccepany filed an application for a lic.ense amendment to increate the gaximum . 1 tmperature for the suppression pool frcxn 95'T to 100 F. By letter of June 11 and tel-conference on June 21, 1990 the NRC requested additional infonnation concerning the effects on the containment dynamic loads which would result frcxn this change.

GSU has reviewed the initial Containment Dynamic Loading ,

-Assessment contained in Appendix 6a of the RBS USAR and i detennined that all loads affectgd by this change were initially '

designed and analyzed at 100 F for the Mark III containment. {

This infonnation was confinned with General Elcctric (NSSS '

vendor) and Stone g Webster (containment design). This original 1 design basis of 100 F (USAR Table 6.2-3) was included in the '

steam condensation loads, all containment dynamic condensation i loads (including condensation oscillation) and ' chugging' loads.

All other factors (e.g., containment pressure and tmperature design limits, ECCS perfonnance, NPSH for safety system pumps and E0P's) remain as discussed in the initial subnittal.

For further information please contact Mr. L. L. Dietrich at (504) 381-4866.

7 Sincerely, b W. H. Odell Manager-Oversight River Bend Nuclear Group TFP/ / pg 9007030089 900626 ' d PDR- ADOCK 05000458

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'U. S. Nuclear Regulatory Cm mission

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