NL-04-081, Proposed Schedule for Reanalysis of Large Break Loss of Coolant Accident
| ML041970366 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/02/2004 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-04-081 | |
| Download: ML041970366 (3) | |
Text
IF-Entergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 9147346700 Fred Dacimo Site Vice President Administration July 2, 2004 Re:
Indian Point Unit No. 2 Docket No. 50-247 NL-04-081 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Proposed Schedule for Reanalysis of Large Break Loss of Coolant Accident
References:
- 1. Consolidated Edison letter to NRC (NL-01-040), "Indian Point Unit 230-day and Annual IOCFR50.46 Report," dated April 10, 2001.
- 2. Entergy letter to NRC (NL-02-057), "Annual 10CFR50.46 Report for Indian Point 2," dated April 24, 2002.
- 3. Entergy letter to NRC (NL-03-1 11), "Annual 1 OCFR50.46 Report for Year 2002 Emergency Core Cooling System Evaluation Changes," dated June 24, 2003.
Dear Sir:
Entergy Nuclear Operations, Inc (Entergy) is proposing to perform a reanalysis of the Large Break Loss of Coolant Accident (LBLOCA) for Indian Point Unit 2 (IP2). A 30-day report, previously submitted for IP2 (Reference 1) pursuant to 10CFR50.46(a)(3)(ii) documented peak clad temperature (PCT) changes greater than 500F. Based on an assessment of the reported changes and as stated in reference 1, a reanalysis was not required. The subsequent annual reports (References 2 and 3) did not change that conclusion for the current licensed power level of 3114.4 MWt.
Entergy is now proposing to perform a reanalysis of LBLOCA at a power level of 3216 MWt using the Advanced Statistical Treatment of Uncertainties Method (ASTRUM). The statistical analysis will be performed for an upgraded fuel design and will include a calorimetric measurement uncertainty of 2%. A transitional assessment will be performed to evaluate the intermediate fuel cycles when the current fuel design is being phased out and replaced with the upgraded fuel N 6O1
NL-04-081 Docket No. 50-247 Page 2 of 2 design. This assessment may result in PCT rackup line items that will be tracked and reported in accordance with I OCFR50.46. Entergy is committing to complete the analysis by April 29, 2005.
The commitment being made in this submittal is stated in Attachment I. If you have any questions or require additional information, please contact Mr. Kevin Kingsley at 914-734-6695.
Si ely,
\\
Fred R. Dacimo ite Vice President Indian Point Energy Center cc:
Mr. Patrick D. Milano, Senior Project Manager Project Directorate I, Division of Reactor Projects I/1l U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555 Mr. Hubert J. Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector's Office Indian Point Unit 2 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Peter R. Smith, President New York State Energy, Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire Plaza Albany, NY 12223
I, ~. A! II.
ATTACHMENT I TO NL-04-081 T
COMMITMENT REGARDING REANALYSIS OF LBLOCA FOR IP2 Number Commitment Due Date NL-04-081-COA Entergy is now proposing to perform a reanalysis of LBLOCA April'29, 2005 at a power level of 3216 MWt using the Advanced Statistical Treatment of Uncertainties Method (ASTRUM). The statistical analysis will be performed for an upgraded fuel design and will include a calorimetric measurement uncertainty of 2%. A transitional assessment will be performed to evaluate the intermediate fuel cycles when the current fuel design is being phased out and replaced with the upgraded fuel design.