ML17256A286

Summary of Telephone Call on 09/06/17, Between NRC and Entergy Concerning Next Steps from the Site Audit on 08/1-3/17

ML17256A286
Person / Time
Site:	Indian Point
Issue date:	09/25/2017
From:	William Burton NRC/NRR/DLR/RPGB
To:	Vitale A Entergy Nuclear Operations
Burton W, 415-6332
References
CAC MD5407, CAC MD5408
Download: ML17256A286 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 25, 2017 Mr. Anthony Vitale Site Vice President, IPECs Entergy Nuclear Operations, Inc.

450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON SEPTEMBER 6, 2017, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC. CONCERNING NEXT ACTIONS FROM THE SITE AUDIT HELD FROM AUGUST 1-3, 2017, PERTAINING TO THE INDIAN POINT, 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 September 6, 2017, to discuss the next actions to be taken and to clarify issues related to the staffs site audit held from August 1-3, 2017, at the Indian Point site. provides a listing of the participants and Enclosure 2 contains a listing of the key issues and next actions.

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:

1. List of Participants

2. Key Issues and Clarifications cc w/encls: Listserv

ML17256A286 OFFICE LA:DLR PM:RPGB:DLR BC:RPGB:DLR PM:RPGB:DLR NAME YEdmonds W Burton S Stuchell W Burton DATE 09/21 /2017 09/21 /2017 09/21 /2017 09/25 /2017/

TELEPHONE CONFERENCE CALL INDIAN POINT UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS SEPTEMBER 6, 2017 PARTICIPANTS AFFILIATIONS Brian Allik U.S. Nuclear Regulatory Commission (NRC)

Steve Bloom NRC William Burton NRC Jim Gavula NRC Bill Holston NRC Albert Wong NRC Charles Caputo Entergy Nuclear Operations, Inc. (Entergy)

Richard Louie Entergy Tom Orlando Entergy Dennis Pennino Entergy Enclosure 1

KEY ISSUES AND CLARIFICATIONS LICENSE RENEWAL APPLICATION SEPTEMBER 6, 2017 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on September 6, 2017, to discuss the next actions and to clarify issues related to the site audit held on August 1-3, 2017, at the Indian Point site. During the exit meeting on August 3, 2017, the staff held a briefing with Entergy personnel to discuss the results of the supplemental audit. Based on finalizing its reviews, the staff identified the following areas as needing additional clarification from the results presented during the exit meeting:

1) Carbon fiber wrap on PAB-204. In addition to the staffs need for information about mid-span degradation, the audit report discusses the staffs need for information relating to the aging effects that need to be managed for the nonmetallic composite material and (if applicable) the aging management program to be used.

2) 904L welds in Unit 3 containment. In addition to the staffs need for information regarding a program update to capture currently planned periodic volumetric inspections of similar welds, the audit report discusses the staffs need for information relating to the adequacy of the acceptance criteria cited in CR-IP3-2016-03607, Corrective Action No. 27. Specifically, the proposed acceptance criteria uses structural integrity from Code Case N-513; however, Unit 3 containment was inoperable due to a pin-hole leak in a service water pipe (not loss of structural integrity from a leak in a service water pipe).

3) Stainless steel inspections not addressed at the exit. Similar to the issue related to the 904L welds, the staff needs additional information regarding inspections of other stainless steel service water components installed inside containment. Entergys supplemental letter dated June 27, 2017, (ADAMS Accession No. ML17187A140) addressed improper material (as it relates to stainless steel) by stating that stainless steel material remains in use but nondestructive examination requirements are already included in the Service Water Integrity program. The staff is only aware of visual nondestructive examination requirements for stainless steel, and as demonstrated by the 904L welds, visual inspections may only identify degradation after containment integrity is lost. Consequently, the staff needs additional information regarding the need for volumetric inspections of any 300 series stainless steel inside containment in order to determine if aging management activities are adequate.

Enclosure 2