NSD-NRC-98-5796, Notifies NRC That Approved Process in WCAP-12488-A Being Used to Account for Design Mods for 17X17 Rfa with Ifm Grid Design as Required by Fcep SER

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Notifies NRC That Approved Process in WCAP-12488-A Being Used to Account for Design Mods for 17X17 Rfa with Ifm Grid Design as Required by Fcep SER
ML20154M323
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 10/13/1998
From: Sepp H
Westinghouse, Div of CBS Corp
To: Collins T
NRC/IRM
References
NSD-NRC-98-5796, NUDOCS 9810200236
Download: ML20154M323 (1)


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Westinghouse Energy Systems Box 355

. Electric Corporation Pittstegh PennsyNania 15230 0355 I October 13,1998 )

NSD-NRC-98-5796  !

U.S. Nuclear Regulatory Commission gv

- ATTN: Document Control Desk h Washington,DC 20555 9-  ;

l Attention: T. E. Collins, Chief l Reactor Systems Branch j j Division of Systems Safety and Analysis i l

Subject:

Fuel Criteria Evaluation Process Notification for the 17X17 Robust Fuel Assembly with IFM Grid Design

Reference:

Letter from N. J. Liparuto (Westinghouse) to J. E. Lyons (NRC), " Transmittal of Response to NRC Request for Information on Wolf Creek Fuel Design Modifications,"

NSD-NRC-97-5189, June 30,1997 1

Dear Mr. Collins:

l The NRC was notified in the above reference that the Westinghouse Fuel Criteria Evaluation Process j

! ~(FCEP) was being used to account for design modifications specific to Wolf Creek fuel. The Wolf Creek ,

L design modifications (i.e., Modified VANTAGE 511 (V511) Lov7 Pressure Drop (LPD) mixing vane grids, 1 Modified V511 Intermediate Flow Mixer (IFM) grids, and thicker walled thimble and instrument tubes) are 1 l now being generically applied to 17X17 V511 fuel in other Westinghouse plants as part of a Robust Fuel Assembly (RFA) program. This letter serves as Westinghouse notification to the NRC, as required by the

[ FCEP SER, that the NRC-approved process in WCAP-12488-A is being used to account for the design

! modifications for the 17X17 RFA with IFM grid design. The above reference concluded that the WRB-2 DNB correlation is applicable to the modified Wolf Creek assembly design. This conclusion also applies to L the generic 17X17 RFA with IFM grid design. Initial application of this generic FCEP notification is planned for the Salem Unit 2 Cycle 11 fuel region which is planned to be inserted into Salem Unit 2 in May 1999.. } l

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l Very truly yours, p' l' I II. A. Sepp, Manager Regulatory and Licensing Engineering -

cc: P. C. Wen, NRR/DRPM/PGEB (10115)

l. 9810200236 981013 i PDR ADOCK 05000482 i P PDR ,

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