ML17173A183

Staff Response to Licensee Submittal of Information Regarding Licensee Action Item No. 6 of Pressurized Water Reactor Vessel Internals Inspection and Evaluation Guidelines (MRP-227-A) (CAC Nos. MF9377-MF9379)

ML17173A183
Person / Time
Site:	Oconee
Issue date:	06/27/2017
From:	Audrey Klett Plant Licensing Branch II
To:	Teresa Ray Duke Energy Carolinas
Klett A, DORL/LPLII-1, 415-0489
References
CAC MF9377, CAC MF9378, CAC MF9379
Download: ML17173A183 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26, 2017 Mr. Thomas D. Ray Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - STAFF RESPONSE TO LICENSEE SUBMITTAL OF INFORMATION REGARDING LICENSEE ACTION ITEM NO. 6 OF PRESSURIZED WATER REACTOR VESSEL INTERNALS INSPECTION AND EVALUATION GUIDELINES (MRP-227-A)

(CAC NOS. MF9377, MF9378, AND MF9379)

By letter dated May 23, 2000 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML003717453), the U.S. Nuclear Regulatory Commission (NRC) issued renewed facility operating licenses to Duke Power Company LLC (renamed Duke Energy Carolinas, LLC (the licensee)) for Oconee Nuclear Station, Units 1, 2, and 3. The staff's review of the licensee's license renewal application is documented in NUREG-1723, "Safety Evaluation Report Related to the License Renewal of Oconee Nuclear Station, Units 1, 2, and 3," dated March 31, 2000 (ADAMS Accession No. ML003695154). As part of its application, the licensee developed an aging management program for the reactor vessel internals, which the NRC approved in NUREG-1723. As part of its license renewal application, the licensee included a regulatory commitment to participate in industry efforts aimed at further understanding the aging effects of the reactor vessel internals and to provide periodic updates to the NRC after completion of significant milestones. This regulatory commitment is discussed in Section 3.4.3.3, "Aging Management Programs for License Renewal," of NUREG-1723.

The joint industry efforts aimed at further understanding the aging effects of reactor vessel internals culminated in the issuance of the Electric Power Research Institute (EPRI) topical report 1016596, "Materials Reliability Program [MRP]: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-Rev. O)," dated December 2008; which EPRI provided to the NRC by letter dated January 12, 2009 (ADAMS Accession No. ML090160212).

By letter dated June 22, 2011 (ADAMS Accession No. ML111600498), the NRC issued its Final Safety Evaluation Report for MRP-227 that endorsed the guidance, provided that eight plant specific actions and seven topical report condition items were implemented. On July 21, 2011, NRC issued Regulatory Issue Summary 2011-07, "License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management" (ADAMS Accession No. ML111990086) to provide guidance to licensees with renewed licenses for the submittal of aging management programs and inspection plans. On December 16, 2011, the. NRC issued Revision 1 of the safety evaluation report for MRP-227-A (ADAMS Accession No. ML11308A770) to ensure the final approved version of MRP-227 (i.e., MRP-227-A) included all NRC required changes. By letter to the NRC dated January 9, 2012 (ADAMS Accession

T. Ray No. ML120170453), EPRI submitted topical report 1022863, "Material Reliability Program:

Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," dated December 2011.

By letter dated November 8, 2010 (ADAMS Accession No. ML103140599), as supplemented, the licensee submitted an amendment request related to its reactor vessel internals inspection plan based on the MRP-227-A. By a supplemental letter dated June 28, 2012 (ADAMS Package Accession No. ML121870231), the licensee committed to submit its evaluation of MRP-227-A, Action Item No. 6. The licensee extended the due date for the commitment by letters dated March 20, 2014 (ADAMS Accession No. ML14086A018, ONS-2014-037), and May 28, 2015 (ADAMS Accession No. ML15159A452, ONS-2015-054). By letter dated June 19, 2015 (ADAMS Accession No. ML15050A671 ), the NRC issued the requested amendments (i.e., Amendment Nos. 392, 394, and 393 for Units 1, 2, and 3, respectively) related to the reactor vessel internals inspection plan.

By letter ONS-2016-047 dated May 26, 2016 (ADAMS Package Accession No. ML16152A128),

the licensee submitted its evaluation of MRP-227-A, Action Item No. 6 and, thus, fulfilled the commitment it made in its letters dated June 28, 2012, March 20, 2014, and May 28, 2015.

If the licensee has any questions regarding this matter, it may contact Ms. Audrey Klett at 301-415-0489 or via email at Audrey.Klett@nrc.gov.

Sincerely, Audrey L. Klett, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

T. Ray

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3-STAFF RESPONSE TO LICENSEE SUBMITTAL OF INFORMATION REGARDING LICENSEE ACTION ITEM NO. 6 OF PRESSURIZED WATER REACTOR VESSEL INTERNALS INSPECTION AND EVALUATION GUIDELINES (MRP-227-A)

(CAC NOS. MF9377, MF9378, AND MF9379)

DATED: JUNE 26, 2017 DISTRIBUTION:

PUBLIC LPL2-1 R/F RidsAcrs_MailCTR Resource RidsNrrDeEvib Resource RidsNrrLAKGoldstein Resource RidsNrrPMOconee Resource RidsNrrDorlLpl2-1 Resource RidsRgn2MailCenter Resource ADAMS A ccess1on No.: ML17173A183 *b" 1 ema1*1 OFFICE NRR/DORL/LPL2-1/PM NRR/DE/EVIB/BC* NRR/DORULPL2-1 /LA NRR/DORULPL2-1/BC NAME AKlett DRudland KGoldstein MMarkley DATE 06/26/17 06/21/17 06/26/17 06/26/17 OFFICE NRR/DORL/LPL2-1 /PM NAME AKlett DATE 06/26/17 OFFICIAL RECORD COPY