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 | *n. | ||
Westinghouse Energy Systems Box 355 | |||
NSD-NRC-98-5796 | . Electric Corporation Pittstegh PennsyNania 15230 0355 I | ||
U.S. Nuclear Regulatory Commission | 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:== | ==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 | 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 | ~(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.. | |||
l Very truly yours, p' l' I II. A. Sepp, Manager Regulatory and Licensing Engineering | } | ||
cc: | \\ 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}} | |||
Latest revision as of 23:57, 10 December 2024
| 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
.. _
/' D l
6
. { ' e*
~
=*
1
- n.
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