View source for NL-06-125, Annual 10 CFR 50.46 Report for Year 2005 - Emergency Core Cooling System Evaluation Changes

{{Adams
| number = ML063620097
| issue date = 12/19/2006
| title = Annual 10 CFR 50.46 Report for Year 2005 - Emergency Core Cooling System Evaluation Changes
| author name = Kansler M
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000247, 05000286
| license number = 
| contact person = 
| case reference number = NL-06-125
| document type = Annual Operating Report, Letter type:NL
| page count = 3
}}

=Text=
{{#Wiki_filter:14VT Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
'ci&#xfd;Enter,&#xfd;                                                                     440 Hamilton Avenue White Plains, NY 10601 Tel 914 2723 200 Fax 914N272320 Michael R. Kansler President December 19, 2006 NL-06-1 25 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

==Subject:==
Indian Point Nuclear Generating Units No. 2 and 3 50-247 and 50-286 Annual 10 CFR 50.46 Report for Year 2005 -
Emerqencv Core Coolinci System Evaluation Chancies

==References:==
: 1. Westinghouse letter (LTR-06-117) 10 CFR 50.46 Annual Notification and Reporting for 2005, dated March 6, 2006.
: 2. Westinghouse letter (IPP-06-23) Indian Point Units 2 and 3 -
10 CFR 50.46 Rackup Sheets Text Clarification, dated March 20, 2006.

==Dear Sir or Madam:==

Entergy Nuclear Operations, Inc. (ENO), has reviewed the 2005 small and large break loss of coolant accident (LOCA) peak clad temperature (PCT) evaluations described in References 1 and 2. The Indian Point Units 2 and 3 small and large break analyses were reviewed by the NRC as part of the Indian Point Units 2 and 3 stretch uprate projects. There were no additional changes to the aforementioned analyses in 2005.
The Indian Point Units 2 and 3 PCTs remain below the maximum fuel clad temperature of 22000 F.
Arce4

There are no commitments contained in this letter. If you have any questions, please contact Ms. Charlene Faison at 914-272-3378.
Very truly your&#xfd;
                                                         )4l*er . Ka President cc: Next page 2

cc:
Mr. Samuel J. Collins Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. John Boska, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555-0001 Resident Inspector's Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511-0059 Resident Inspector's Office Indian Point Unit 2 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511-0059 Mr. Paul Eddy NYS Department of Public Service 3 Empire State Plaza Albany, NY 12223 Mr. Peter R. Smith President NYSERDA 17 Columbia Circle Albany, NY 12203 3}}