ML13022A047: Difference between revisions

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{{Adams
#REDIRECT [[BVY 13-002, Changes in Peak Cladding Temperature Emergency Core Cooling System Loss of Coolant Accident Analysis Annual Report for 2012]]
| number = ML13022A047
| issue date = 01/14/2013
| title = Changes in Peak Cladding Temperature Emergency Core Cooling System Loss of Coolant Accident Analysis Annual Report for 2012
| author name = Wanczyk R J
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person =
| case reference number = BVY 13-002
| document type = Letter, Annual Operating Report
| page count = 2
}}
 
=Text=
{{#Wiki_filter:Entergy Nuclear Operations, Inc.Vermont Yankee 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 Robert J. Wanczyk Licensing Manager BVY 13-002 January 14, 2013 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
 
==SUBJECT:==
1OCFR50.46(a)(3)(ii)Annual Report for 2012 Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
 
==REFERENCES:==
 
(1) Global Nuclear Fuel Report, 0000-0128-35"75-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 28 Cycle 29, dated August 2011 (2) Global Nuclear Fuel Report, 0000-0146-9245-SRLR, Revision 0, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 29 Cycle 30, dated December 2012 (3) Letter, Entergy to USNRC, Vermont Yankee Nuclear Power Station 10CFR50.46(a)(3)(ii)
Report, BVY 12-003, dated January 6, 2012
 
==Dear Sir or Madam:==
This letter is to report, in accordance with 1 OCFR50.46(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 Cycle 29 from January 2012 to December 2012.For Cycle 29, VY used the General Electric (GE) SAFER/GESTR methodology for the evaluation of the ECCS/LOCA.
The results are summarized and reported in Reference (1).The licensing basis PCT, calculated for the GE14 and GNF2 fuel types VY currently has loaded in its core, including corrections through December 2011, is documented in Reference (3).There was one error notification identified for VY fuel in 2012 as reported in the following table and listed in Reference (2).
BVY 13-002 / page 2 of 2 Summary of 1OCFR50.46 Changes/Errors for Vermont Yankee (2012)10CFR50.46 Change/Error 10CFR50.46 Change/Error Licensing Basis Delta Identification Description PCT (degF) for: GE14 GNF2 2012-01 PRIME Implementation
+35 I +35 Total Delta PCT +35 I +35 Previous Licensing Basis 2005 I 2105 PCT from Reference (3)Adjusted Licensing Basis 2040 I 2140 PCT Since the PCT for the GE14 and GNF2 fuel types are within the acceptance criterion of 10CFR50.46(b)(1), there is no need for re-analysis or other action per 1 0OCFR50.46(a)(3)(ii).
There are no new regulatory commitments being made in this submittal.
If you have any questions with this submittal, please contact me at (802) 451-3166.Sincerely,[RJW/JTM]cc: Mr. William M. Dean, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Richard Guzman, 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 Vernon, VT 05354 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601}}

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