NL-09-029, Supplemental Information Regarding Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination

Supplemental Information Regarding Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination

ML090720586
Person / Time
Site:	Indian Point
Issue date:	03/03/2009
From:	Robert Walpole Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-09-029, TAC MD9196, TAC MD9197
Download: ML090720586 (2)

Text

Indian Point Energy Center

• --Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 Robert Walpole Licensing Manager Tel 914 734 6710 March 3, 2009 Re: Indian Point Unit 2 and 3 Docket Nos. 50-247 and 50-286 NL-09-029 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Supplemental Information Regarding Request For Relief To Extend The Unit 2 and 3 Inservice Inspection Interval For The Reactor Vessel Weld Examination (TAC Nos. MD9196 and MD9197)

Reference:

1. Entergy Letter dated July 8, 2008, NL-08-096, "Request For Relief To Extend The Unit 2 and 3 Inservice Inspection Interval For The Reactor Vessel Weld Examination And Request For License Amendment For Submittal of ISI Information and Analyses"

2. Entergy Letter dated December 23, 2008, NL-08-177, "Response to Request For Additional Information on Request For Relief To Extend The Unit 2 and 3 Inservice Inspection Interval For The Reactor Vessel Weld Examination (TAC Nos. MD9196 and MD9197)"

3. Entergy Letter dated January 20, 2009, NL-09-003, "Supplemental Response to Request For Additional Information on Request For Relief To Extend The Unit 2 and 3 Inservice Inspection Interval For The Reactor Vessel Weld Examination (TAC Nos. MD9196 and MD9197)"

4. Entergy Letter dated April 23, 2007, NL-07-039, "License Renewal Application"

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (Entergy) submitted a relief request, Reference 1, and provided supplemental information in References 2 and 3. During a phone conversation the NRC asked for verification that the reactor vessel fluence provided in the license renewal application was applicable to this relief request. The reactor vessel fluence is discussed in Reference 2, question 6. The references identified in the discussion as the source for the 48 EFPY fluence values are the same references from which 48 EFPY fluence values were obtained for Section 4.2, "REACTOR VESSEL NEUTRON EMBRITTLEMENT" of the license

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NL-09-029 Docket Nos. 50-247 and 50-286 Page 2 of 2 renewal application. The original submittal, Reference 4, has been supplemented via subsequent communications. The license renewal application evaluations used a single bounding 48 EFPY fluence value for each unit, while the relief request evaluations used values for specific vessel locations.

There are no new commitments being made in this submittal.

If you have any questions or require additional information, please contact me at (914) 734-6710.

A-,- Robert Walpole Licensing Manager Indian Point Energy Center cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service Mr. Robert Callender, Vice President NYSERDA