ML080390537: Difference between revisions

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| number = ML080390537
| number = ML080390537
| issue date = 02/04/2008
| issue date = 02/04/2008
| title = 10 CFR 50.46(a)(3)(ii) Annual Report for 2007
| title = CFR 50.46(a)(3)(ii) Annual Report for 2007
| author name = Sullivan T A
| author name = Sullivan T
| author affiliation = Entergy Nuclear Operations, Inc
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =  
| addressee name =  
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==References:==
==References:==
(a) Global Nuclear Fuel Report, 0000-0035-6536-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 25/Cycle 26, March 2007.(b) Global Nuclear Fuel Report, 0000-0035-6443-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear, Power Station Reload 24/Cycle 25 (with Extended Power Uprate), December 2005.(c) Entergy Nuclear Northeast Letter, Ted A. Sullivan (Entergy) to USNRC, Vermont Yankee Nuclear Power Station 1 OCFR50.46(a)(3)(ii)
(a) Global Nuclear Fuel Report, 0000-0035-6536-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 25/Cycle 26, March 2007.(b) Global Nuclear Fuel Report, 0000-0035-6443-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear, Power Station Reload 24/Cycle 25 (with Extended Power Uprate), December 2005.(c) Entergy Nuclear Northeast Letter, Ted A. Sullivan (Entergy) to USNRC, Vermont Yankee Nuclear Power Station 1 OCFR50.46(a)(3)(ii)
Annual Report for 2006, BVY 07-006, January 17, 2007.
Annual Report for 2006, BVY 07-006, January 17, 2007.



Revision as of 15:58, 12 July 2019

CFR 50.46(a)(3)(ii) Annual Report for 2007
ML080390537
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 02/04/2008
From: Ted Sullivan
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 08-05
Download: ML080390537 (3)


Text

Entergy Nuclear Operations, Inc.Vermont Yankee P.O. Box 0250 E nte y320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 February 4, 2008 BVY 08-05 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

References:

(a) Global Nuclear Fuel Report, 0000-0035-6536-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 25/Cycle 26, March 2007.(b) Global Nuclear Fuel Report, 0000-0035-6443-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear, Power Station Reload 24/Cycle 25 (with Extended Power Uprate), December 2005.(c) Entergy Nuclear Northeast Letter, Ted A. Sullivan (Entergy) to USNRC, Vermont Yankee Nuclear Power Station 1 OCFR50.46(a)(3)(ii)

Annual Report for 2006, BVY 07-006, January 17, 2007.

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)1OCFR50.46(a)(3)(ii)

Annual Report for 2007 This letter is to report, in accordance with 1OCFR50.46(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 25 and 26 from.----January 2007 to December 2007.For Cycles 25 and 26, 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), (b)and (c).The licensing basis PCT, calculated for the GE14 fuel type VY currently has loaded in its core, including corrections through 2006, 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 2007.

BVY 08-05 / page 2 Summary of 10CFR50.46 Changes/Errors for Vermont Yankee (2007)1OCFR50.46 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 1OCFR50.46(b)(l), 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, Ted A. Sqllivan)Site Vicý_Pesient 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 Section II Correspondence Screening Does this letter contain commitments?

If "yes," identify the commitments'with due dates Yes El in the submittal and in Section III. No [Does this letter contain any information or analyses of new safety issues performed at NRC Yes L]request or to satisfy a regulatory requirement?

If "yes," reflect requirement to update the No [UFSAR in Section II1..Does this letter require any document changes (e.g., procedures, DBDs, FSAR, TS Bases, Yes EL etc.), if approved?

If "yes," indicate in Section III an action for the responsible No [department to determine the affected documents. (The Correspondence Preparer may indicate the specific documents requiring revision, if known or may initiate an action for review.)Does this'letter contain information certified accurate?

If "yes," identify the information and Yes LI document certification in an attachment. (Attachment 9.5 may be used.) No [Section III Action Items Required Actions Due Date Responsible Dept.Note: Actions needed upon approval should be captured in the appropriate action tracking system None Section IV Final Document Signoff for Submittal Correspondence Preparer J. Meyer ./f '- //z:7/0o Final Submittal Review W. Limberger

,. ,/o i, Responsible Department Head D. Mannai 1,