ML13318A450

Request for Additional Information for the Review of the Indian Point Nuclear Generating, Units 2 and 3, License Renewal Application, Set 2013-06 (TAC Nos. MD5407 and MD5408)

ML13318A450
Person / Time
Site:	Indian Point
Issue date:	11/19/2013
From:	Kimberly Green NRC/NRR/DLR/RASB
To:	Entergy Nuclear Operations
Green K, 415-1627
References
TAC MD5407, TAC MD5408
Download: ML13318A450 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2013-06 (TAG NOS. MD5407 AND MD5408)

Dear Sir or Madam:

By letter dated Apri123, 2007, as supplemented by letters dated May 3, 2007, and June 21. 2007, Entergy Nuclear Operations, Inc. (Entergy), submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3), for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff documented its findings in the Safety Evaluation Report (SER) related to the license renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, which was issued August 2009 and supplemented August 30, 2011 (SER Supplement 1).

By letter dated July 14, 2010, Entergy amended its license renewal application (LRA) and submitted the Indian Point Nuclear Generating Unit Nos. 2 and 3 Reactor Vessel Internals (RVI)

Program. By letter dated September 28, 2011, as supplemented by letter dated February 17, 2012, Entergy submitted the "Indian Point Energy Center Reactor Vessel Internals Inspection Plan" (RVIInspection Plan). The RVIInspection Plan, as supplemented, was intended to be consistent with the Nuclear Regulatory Commission (NRC)-approved Electric Power Research Institute (EPRI) topical report, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," (MRP-227-A), and to partially fulfill Commitment 30 associated with the IP LRA.

By letter dated May 15, 2012, the staff requested additional information regarding the Indian Point RVI Program and RVIInspection Plan. Entergy provided a partial response to the staff's request for additional information (RAI) by letter dated June 14, 2012, and provided the remainder of the response by letter dated September 28, 2012, including a response to RAI 6, related to ApplicanULicensee Action Item 1 from MRP-227 -A. Subsequent to receiving Entergy's response to RAI 6, the NRC staff and EPRI met on November 28, 2012 (ADAMS Accession No. ML13014A672), January 22-23, 2013 (ADAMS Accession No. ML13042A048),

and February 25, 2013 (ADAMS Accession No. ML13067A262) to facilitate development of a generic approach for resolution of ApplicanULicensee Action Item 1.

The staff is therefore issuing the enclosed follow-up RAI 6-A, which is based on the two questions that industry and the NRC staff agreed upon during the January 22-23, 2013, closed meeting, as modified by the February 25, 2013, teleconference as sufficient for verification of plant-specific applicability for Westinghouse-design RVI.

This RAI was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 60 days from the date of this letter. If you have any questions, please contact me at 301A15-1627, or by e-mail at Kimberly.Green@nrc.gov.

Sincerely, i<.JJJ~

Kimberly Green, Sr. Mechanical Engineer Aging Management of Structures, Electrical, and Systems Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosure:

As stated cc: Listserv

• .. ML13318A450 *concurred via email OFFICE LA:DLR/RPB1* APM: DLR/RASB BC DLR/RPB1 APM: DLR/RASB NAME YEdmonds KGreen YDiaz-Sanabria KGreen DATE 11/18/13 11/18/13 11/19/13 11/19/13

REQUESTS FOR ADDITIONAL INFORMATION SET 2013-06 RELATED TO INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION REACTOR VESSEL INTERNALS PROGRAM AND INSPECTION PLAN DOCKET NOS 50-247 AND 50-286 RAI6-A As discussed in References 1 and 2, provide the following information related to verification of the applicability of MRP-227-A to Indian Point Nuclear Generating Unit Nos. 2 and 3 {IP2 and IP3):

1 Do the IP2 or IP3 reactor vessel internals (RVI) have non-weld or bolting austenitic stainless steel components with 20 percent cold work or greater, and if so, do the affected components have operating stresses greater than 30 ksi? If so, perform a plant-specific evaluation to determine the aging management requirements for the affected components.

2. Has IP2 or IP3 ever utilized atypical fuel design or fuel management that could make the assumptions of MRP-227 -A regarding core loading/core design non-representative for that unit, including power changes/uprates? If so, describe how the differences were reconciled with the assumptions of MRP-227-A, or provide a plant-specific aging management program for affected components as appropriate.

References

1. Meeting Summary EPRI-Westinghouse January 22-23, 2013, February 21, 2013 (ADAMS Accession No. ML13042A048)

2. 2/25/2013 Summary of Telecom with EPRI and Westinghouse Electric Company, March15, 2013 (ADAMS Accession No. ML13067A262)

ENCLOSURE

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2013-06 (TAC NOS. MD5407 AND MD5408)

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