RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in

Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in

ML20207D258
Person / Time
Site:	River Bend
Issue date:	05/26/1999
From:	King R ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBFI-99-0179, RBFI-99-179, RBG-45021, NUDOCS 9906030280
Download: ML20207D258 (2)

Text

'

Ent:rgy oper ti:ni, Inc.

/- m' River Bond Station

[ f 5485 U S. Highway 61 f

P. O. Box 220

'. h St. Franciswile, LA 70775 Tel 225 336 6225 Fax 225 635 5068

=

i Rick J. King Duector

! Nuclear Safety & Regulatory Affairs 1

1 May 26,1999 4 l

l U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Minimum Critical Power Ratio Safety Limits License Amendment 105 File Nos. G9.5, G9.42 RBG-45021 RBF1-99-0179 i

Ladies and Gentlemen:

l l

The purpose of this letter is to inform you that Cycle 9 operation of River Bend Station (RBS) will remain within the minimum critical power ratio (MCPR) safety limits ,

approved in Amendment 105 to the RBS Technical Specifications, issued by the NRC in  ;

a letter dated April 27,1999. The NRC's Safety Evaluation for Amendment 105 discusses the analysis for the Cycle 9 core as being based on a full core of gel 1 fuc!

bundles.

As a result of our inspection of Cycle 8 fuel, we have conservatively decided to defer reloading any of the Cycle 8 first-bumed gel 1 (HGE) fuel bundles. By eliminating the HGE fuel from the available fuel bundles for Cycle 9, the core design will continue to be 0  ;

a mix of GE8 and gel 1 fuel bundles. Therefore, the reanalysis for the Cycle 9 core is ,

based on a core consisting of both GE8 and GE11 fuel. However, the NRC-approved l

General Electric (GE) methodologies, discussed in the Safety Evaluation, continue to be 1 l those used for the Cycle 9 modified core. GE reanalyzed the Cycle 9 core using the 0' L

NRC-approved methodologies discussed in the Safety Evaluation for Amendment 105, kO i

and determined that the limits in Amendment 105 provide conservative margin and are bounding.

n W WM Wyda 2 P

l

p: -

I

! l

!- 4:*.-

l ~~

Minimum Critical Power Ratio Safety Limits Licase Amendment 105

, RBG-45021 -

L RBF1-99-0179

l. May 26,1999 l Page 2 of 2

-]

In summary, the NRC-approved methodologies are used and the MCPR safety limits )

l- approved in Amendment 105 remain bounding. Because these conditions are met for the j f '

Cycle 9 core, we have concluded that the intent of the NRC's Safety Evaluation for Amendment 105 remains effective and that no further NRC approval is necessary.

We have determined that there are no commitments contained in this letter. If you have questions regarding this matter, please contact Patricia Campbell at 225-381-4615.

Sincerely, 1

,y */

Rick J. King ,

i l

CC: U. S. Nuclear Regulatory Commission .)

Region IV 611 Ryan Plaza Drive, Suite 400 ,

Arlington,TX 76011 i H

NRC Sr. Resident Inspector P. O. Box 1050-St.Francisville,LA 70775.

i l Robert Fretz i U. S. Nuclear Regulatory Commission Mail Stop O-13D-18 j Washington,DC 20555 l l

l l

i

. _ . . j