BVY 09-004, CFR 50.46(a)(3)(ii) Annual Report for 2008

CFR 50.46(a)(3)(ii) Annual Report for 2008

ML090090208
Person / Time
Site:	Vermont Yankee
Issue date:	01/06/2009
From:	Michael Colomb Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 09-004
Download: ML090090208 (2)

Text

Entergy Nuclear Operations, Inc.

Vermont Yankee P.O. Box 0250

- Entergy 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 January 6, 2009 BVY 09-004 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

References:

(a) Global Nuclear Fuel Report, 0000-0078-8270-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 26/Cycle 27, September 2008 (b) Global Nuclear Fuel Report, 0000-0059-6536-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 25/Cycle 26, March 2007 (c) Entergy Letter, Ted A. Sullivan (Entergy) to USNRC, Vermont Yankee Nuclear Power Station 10CFR50.46(a)(3)(ii) Annual Report for 2007, BVY 08-05, February 4, 2008

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) 10CFR50.46(a)(3)(ii) Annual Report for 2008

Dear Sir or Madam,

This letter is to report, in accordance with 10CFR50.46(a)(3)(ii), changes in peak cladding temperature (PCT) for the Vermont Yankee (VY) Emergency Core Cooling System (ECCS) Loss of Coolant Accident (LOCA) analysis. This annual report covers VY Cycles 26 and 27 from January 2008 to December 2008.

For Cycles 26 and 27, VY used the General Electric (GE) SAFER/GESTR methodology for the evaluation of the ECCS/LOCA. The results are summarized and reported in References (a) and (b).

The licensing basis PCT, calculated for the GE14 fuel type VY currently has loaded in its core, including corrections through 2007, is documented in Reference (c).

In Cycle 26 VY loaded four GNF2 Lead Use Assemblies (LUAs) into the core. Since these assemblies were loaded as LUAs, the PCT change associated with these assemblies is not included in this annual report.

The following table updates the results to reflect subsequent changes to or errors identified in the methodology for the current VY fuel type. There were no new changes or error reports identified for VY fuel in 2008.

,46o,2,

BVY 09-004 / page 2 Summary of 10CFR50.46 Changes/Errors for Vermont Yankee (2008) 10CFR50.46 Change/Error 10CFR50.46 Change/Error Licensing Basis Delta PCT Identification Description (degF) for GE14 None N/A N/A Total Delta PCT 0 Previous Licensing Basis PCT 1960 from Reference (c)

Adjusted Licensing Basis PCT 1960 Since the PCT for the GE14 fuel type is well within the acceptance criterion of 10CFR50.46(b)(1), there is no need for re-analysis or other action per 10CFR50.46(a)(3)(ii).

There are no new regulatory commitments being made in this submittal.

If you have any questions concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.

Sincerely, Michael J. b-Site Vice President Vermont Yankee Nuclear Power Station cc: Mr. Samuel J. Collins, Region I Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 'State Street, Drawer 20 Montpelier, VT 05620-2601