BVY 04-005, Technical Specification Proposed Change No. 257 Implementation of Arts/Mellla at Vermont Yankee Correction of Peak Cladding Temperature for GE13 Fuel

Technical Specification Proposed Change No. 257 Implementation of Arts/Mellla at Vermont Yankee Correction of Peak Cladding Temperature for GE13 Fuel

ML040280473
Person / Time
Site:	Vermont Yankee
Issue date:	01/20/2004
From:	Thayer J Entergy Nuclear Vermont Yankee, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 04-005, NEDC-33089
Download: ML040280473 (2)

Text

,- Entergy Nuclear Vermont Yankee, LLC E n terAgy Entergy Nuclear Operations, Inc.

185 Old Ferry Road Brattleboro, VT 05302-0500 January 20, 2004 BVY 04-005 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

Technical Specification Proposed Change No. 257 Implementation of ARTS/JIELLLA at Vermont Yankee Correction of Peak Claddin! Temperature for GE13 Fuel By letter dated March 20, 20031, Vermont Yankee 2 (VY) proposed to amend Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station (VYNPS) by implementing an expanded power-to-flowv operating domain based on the Average Power Range Monitor, Rod Block Monitor Technical Specifications/Maximuim Extended Load Line Limit Analysis (ARTS/MELLLA) methodology. In support of the license amendment request (LAR) and the new operating limits, VY provided, as part of its application (as Attachments 5 and 6 to the March 20, 2003 letter), proprietary and non-proprietary versions of plant-specific safety analysis prepared by GE Nuclear Energy, NEDO-33089 3 .

Section 6.0 of NEDC-33089 presents the results of the design basis loss-of-coolant accident analysis for VYNPS using SAFER/GESTR methodology. For MELLLA, a peak cladding temperature (PCT) of 19100 F was determined for GE13 fuel and reported on page 6-1 of NEDC-33089. GE Nuclear Energy has provided a IOCFR50.46 notification to VY that states, due to an input error that was inadvertently made in the SAFER analysis, the limiting case PCT for GE13 fuel in this analysis should actually be 100 F less, or 1900 0 F. The error, which is applicable to GE13 fuel analyses only, occurred in SAFER input data regarding the jet pump mixing length and main steam isolation valve closure time. Accordingly, VY is hereby revising the analytical results reported in NEDC-33089 in this regard.

This supplement to the LAR does not change the scope or conclusions in the original application, nor does it change the no significant hazards consideration determination.

Vermont Yankee letter to U.S. Nuclear Regulatory Commission, "Technical Specification Proposed Change No. 257, Implementation of ARTS/MELLLA at Vermont Yankee," BVY 03-23, March 20,2003.

2 Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. are the licensees of the Vermont Yankee Nuclear Power Station.

3 NEDO-33089, "Vermont Yankee Nuclear Power Station, APRM/RBM/Technical Specifications /

Maximum Extended Load Line Limit Analysis (ARTS/MELLLA)," March 2003.

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BVY 04-005 / Page 2 If you have any questions in this regard, please contact Mr. Len Gucwa at (802) 258-4225.

Sincerely,

,1*P~'

ay . layer We Vice President STATE OF VERMONT

)

WINDHAM COUNTY Then personally appeared before me, Jay K. Thayer, who, being duly sworn, did state that he is Site Vice President of the Vermont Yankee Nuclear Power Station, that he is duly authorized to execute and file the foregoing document, and that the statements therein are true to the best of his knowledge and belief.

Sally A. Sanidstrur6, Notary Pub rc:,d5V,-

My Commission Expires Februry-,'O, 2007 cc: USNRC Region I Administrator t \

USNRC Resident Inspector- VYNPS USNRC Project Manager - VYNPS '

Vermont Department of Public Service