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: Difference between revisions

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Westinghouse                 Energy Systems                                           Box 355
*n.
            . Electric Corporation                                                                   Pittstegh PennsyNania 15230 0355 I                                                                                                     October 13,1998                                   )
Westinghouse Energy Systems Box 355
NSD-NRC-98-5796                                   !
. Electric Corporation Pittstegh PennsyNania 15230 0355 I
U.S. Nuclear Regulatory Commission                                                                                           gv
October 13,1998
            - 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
NSD-NRC-98-5796 U.S. Nuclear Regulatory Commission gv h
- ATTN: Document Control Desk 9-Washington,DC 20555 Attention:
T. E. Collins, Chief Reactor Systems Branch j
j Division of Systems Safety and Analysis i
l


==Subject:==
==Subject:==
Line 35: Line 39:
==Reference:==
==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,"
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
NSD-NRC-97-5189, June 30,1997 1


==Dear Mr. Collins:==
==Dear Mr. Collins:==
 
l The NRC was notified in the above reference that the Westinghouse Fuel Criteria Evaluation Process j
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
!            ~(FCEP) was being used to account for design modifications specific to Wolf Creek fuel. The Wolf Creek                                   ,
design modifications (i.e., Modified VANTAGE 511 (V511) Lov7 Pressure Drop (LPD) mixing vane grids, Modified V511 Intermediate Flow Mixer (IFM) grids, and thicker walled thimble and instrument tubes) are l
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
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
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
                                                                                                                                            \ D J
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 Very truly yours, p' l' I II. A. Sepp, Manager Regulatory and Licensing Engineering                                 -
}
cc:     P. C. Wen, NRR/DRPM/PGEB (10115)
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: l.               9810200236 981013 i               PDR     ADOCK 05000482 i               P                         PDR         ,
l Very truly yours, p' l' I II. A. Sepp, Manager Regulatory and Licensing Engineering cc:
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P. C. Wen, NRR/DRPM/PGEB (10115) l.
9810200236 981013 i
PDR ADOCK 05000482 i
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Latest revision as of 23:57, 10 December 2024

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 
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)


Text

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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 h

- ATTN: Document Control Desk 9-Washington,DC 20555 Attention:

T. E. Collins, Chief 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, Modified V511 Intermediate Flow Mixer (IFM) grids, and thicker walled thimble and instrument tubes) are 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..

}

\\ D J

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 I

J