RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required

From kanterella
Jump to navigation Jump to search
Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required
ML20216J898
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/30/1999
From: King R
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBF1-99-0278, RBG-45123, NUDOCS 9910060307
Download: ML20216J898 (2)


Text

g Ent:rgy Oper;tions, Inc.

,[N, \ River Bend Station l 5485 U.S. Highway 61 J J. P. O. Box 220

,+

'g*bh St. Francisville LA 70775 Tel 225 336 6225 Fax 225 635 5068  ;

Rick J. King j Director Nuclear Safety Assurance  !

l 1

September 30,1999 U. S. Nuclear Regulatory Commission Attn: Document Control Desk l Washington, DC 20555

Subject:

River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 10 CFR 50.46 (a)(3)(ii) Report l l l File Nos. G9.5 RBG-45123

.RBF1-99-0278 Ladies and Gentlemen:

In accordance with 10 CFR 50.46 (a)(3)(ii), River Bend Station (RBS) is required to report I changes to or errors discovered in acceptable ECCS evaluation models on an annual basis.

RBS is obligated to report the nature of the change or error and its estimated effect on calculated Peak Clad Temperature (PCT).

. Individual changes and errors affecting the RBS ECCS evaluation model have also been reported to the NRC by General Electric (GE). The related GE correspondence, letter to NRC Document Control Desk dated June 30,1999, which discusses these changes and/or errors in detail.

The error resulted from changes to the SAFER code models counter current flow limiting ,

(CCFL) in the upper part of the fuel bundle at the upper tie plate (UTP). This change only j applies to GE 8 fuel design in the RBS reactor. The effect of the change was evaluated and  ;

' determined to be +5 to +25 F, which is less than the current limiting upper bound PCT and  ;

licensing basis PCT, which are based on GE 11 fuel. Because the change only affected non- l funiting locations, no changes to the SAR or the COLR were required.

l. ~

0 9910060307 990930 0%

PDR ADOCK 05000458 P PDR ' D

P -

D ' 10 CFR 50.46 (aX3Xii) Report

, September 30,1999 RBG-45123 RBF1-99-0278 '

Page 2 of 2' For further information, contact Mr. B. M. Burmeister at (225) 381-4148.

Sincerely,

. ~

RJK/BMB cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011 NRC Sr. Resident inspector P. O. Box 1050 -

St. Francisville, LA 70775 -

INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-3064-Mr. Jim Calloway

. Public Utility Commission ofTexas 1701 N. Congress Avenue Austin,TX 78711-3326 i

Louisiana Department of Environmental Quality Radiation Protection Division P. O. Box 82135 '

Baton Rouge, LA 70884-2135 ATTN: Administrator'-

l 9

l