ML17191A456

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06/08/2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01
ML17191A456
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 09/20/2017
From: William Burton
Division of License Renewal
To:
Entergy Nuclear Operations
William Burton, NRR/DLR, 415-6332
References
CAC MD5407, CAC MD5408
Download: ML17191A456 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 20, 2017 LICENSEE: Entergy Nuclear Operations, Inc.

FACILITY: Indian Point Unit Nos. 2 and 3

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JUNE 8, 2017, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION (CAC. NOS. MD5407 AND MD5408)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., (Entergy) held a telephone conference call on June 8, 2017, to discuss and clarify portions of Entergys response to request for additional information (RAI) related to ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components, (see ADAMS Accession No. ML17145A288). provides a listing of the participants at the RAIs telephone conference call and summarizes the key points discussed with the applicant in the telephone conference.

Entergy had an opportunity to comment on this summary.

Sincerely,

/RA/

William Burton, Senior Project Manager Projects Management and Guidance Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosures:

List of Participants cc w/encls: Listserv

ML17191A456 OFFICE PM:MRPB:DLR LA:DLR BC:MRPB:DLR PM:MRPB:DLR NAME WBurton YEdmonds SStuchell WBurton DATE 9/1/2017 9/20/2017 9/20/2017 9/20/2017

TELEPHONE CONFERENCE CALL INDIAN POINT UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JUNE 8, 2017 PARTICIPANTS AFFILIATIONS Araceli Billoch U.S. Nuclear Regulatory Commission (NRC)

Theresa Buchanan NRC William Butch Burton NRC Seung Min NRC Sheldon Stuchell NRC Nelson Azevedo Entergy Nuclear Operations, Inc. (Entergy)

Richard Burroni Entergy Alan Cox Entergy Robert Dolansky Entergy Richard Louie Entergy Enclosure 1

CLARIFICATION TELECONFERENCE CALL RELATED TO ENTERGYS RESPONSE TO ISG-2016-01 LICENSE RENEWAL APPLICATION JUNE 8, 2017 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy held a telephone conference call on June 8, 2017, to discuss and clarify information concerning the license renewal application (LRA).

By letter dated May 19, 2017 (ADAMS Accession No. ML17145A288), Entergy Nuclear Operations, Inc. (Entergy) provided responses to NRC staff requests for additional Information (ADAMS Accession No. ML17088A327). Upon review of Entergys responses, the NRC staff determined that additional clarification was necessary. On June 8, 2017, the staff held a teleconference with Entergy to discuss the needed clarifications.

Entergy clarified that the visual inspections under the Steam Generator Integrity Program on channel head interior areas are consistent with LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. These inspections are intended to identify signs indicating cracking or loss of material is occurring (e.g., rust stains, gross cracking, distortion of divider plates, and cladding breach). The inspections also confirm the structural integrity of reactor coolant pressure boundary components such as channel heads and tubesheets. In addition, Entergy discussed the recent general visual inspection activities for the channel head interior areas and plans for future inspections.

The staff agreed that these inspections under Entergys program are consistent with the guidance in LR-ISG-2016-01 and can identify signs indicating cracking in divider plate assembles and tube-to-tubesheet welds and loss of material in channel heads and tubesheets (such as loss of material due to boric acid corrosion). The staff has no further concerns with adherence to LR- ISG-2016-01.

Enclosure 2