NL-15-1507, Units 1 and 2 - License Renewal Commitment Item 6
| ML15226A227 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/12/2015 |
| From: | Pierce C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-15-1507 | |
| Download: ML15226A227 (4) | |
Text
Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992,7601 SOUTHERN ~
A SOUTHERN COMPANY AUG 1-2 2015 Docket Nos.: 50-348 50-364 NL-1 5-1 507 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 License Renewal Commitment Item 6 Ladies and Gentlemen:
Commitment Item No. 6 of NUREG-1 825, the Safety Evaluation Report (SER) for the renewed operating license for Joseph M. Farley Nuclear Plant (FNP) Units 1 and 2 requires:
"The new FNP Reactor Vessel Internals (RVI) Program will be implemented prior to entering the period of extended operation to provide an integrated inspection program that addresses the reactor internals. It will supplement the inspection requirements of ASME Section Xl, IWB Categor'y B-N-3 to ensure that aging effects do not result in a loss of intended function of internal components during the period of extended operation.
SNC will continue to participate in industry initiatives intended to clarify the nature and extent of aging mechanisms potentially affecting the FNP reactor internals. SNC will incorporate the results of these initiatives into the RVI Program. FNP will submit an inspection plan for the RVI Program for NRC review and approval at least 24 months prior to entering the periods of extended operation for the FNP units."
In a measure to improve the efficiency of licensee development and staff review, it was mutually agreed that the submission of the inspection plan for the Reactor Internals Program for Nuclear Regulatory Commission (NRC) review and approval could be made for both units 22 months prior to entering the periods of extended operation for the FNP Unit 1. Since establishing the original commitments the industry and NRC continued its strategy to proceed with a generic approach through the review and approval of technical reports provided by the Materials Reliability Program (MRP). The technical basis for the scope, periodicity, nondestructive examination requirements, and acceptance criteria are now generically approved through staff safety evaluation and issuance of MRP-227-A and associated licensee actions to demonstrate plant-specific 4Q9c7
U.S. Nuclear Regulatory Commission NL-15-15O7 Page 2 applicability. This has been documented via Regulatory Issue Summary (RIS) 2011-07 and Interim Staff Guidance (ISG) LR-ISG-201 1-04. In order to meet the current guidance, Southern Nuclear Operating Company (SNC) contracted Westinghouse Electric Company (WEC) to prepare plant-specific aging management plans. They are provided as Enclosures 1 and 2 of this correspondence and are intended to meet the intent of the original inspection plan submittal and the more current guidance of the RIS and ISG. As part of the FNP plant-specific review of reactor internals components versus the generic list of components evaluated for the Westinghouse design, a singular component item (control rod guide tube (CRGT) guide cards) was found to be potentially different in material specification than assumed by the WEC expert panel (cast versus wrought austenitic stainless was a specification option). This potential difference, which is only applicable to FNP Unit 1, was evaluated by Westinghouse and found not to warrant any changes to the industry guidance for CRGT guide cards.
When the FNP license renewal application was submitted, NUREG 1801 revision 0 was the approved version. Since then, more recent versions of the Generic Aging Lessons Learned (GALL) have been issued. The aging management program (AMP) for management of reactor internals is now XI.M16A. The recent requirements have been reviewed and FNP meets these later provisions as well.
To document this, a Final Safety Analysis Report (Chapter 18) update was processed to reflect the incorporation of the most recent staff and industry guidance into the FNP reactor internals AMP description.
The commitment to establish a new RVI Program has been accomplished and is outlined in the two enclosures. The commitment to participate in the industry initiatives is a continuing commitment that is fulfilled through SNC's continuing participation in the NEI 03-08, Guideline for the Management of Materials Issues.
This letter contains no new NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Sincerely C.R. Pierce Regulatory Affairs Director CRP/GLS/lac
Enclosure:
- 1. PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at J.M. Farley Nuclear Plant Unit 1
- 2. PWR Vessel Internals Program. Plan for Aging Management of Reactor Internals at J.M. Farley Nuclear Plant Unit 2
U.S. Nuclear Regulatory Commission NL-15-1507 Page 3 cc:
Southern Nuclear Operatingq Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. M. D. Meier, Vice President - Regulatory Affairs Mr. D. R. Madison, Vice President - Fleet Operations Mr. B. J. Adams, Vice President - Engineering Ms. B. L. Taylor, Regulatory Affairs Manager - Farley RTYPE: CFAO4.054 U. S. Nuclear Regqulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager - Farley Mr. P. K. Niebaum, Senior Resident Inspector - Farley Alabama Department of Public Health.
Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant - Units 1 and 2 License Renewal Commitment Item 6 PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at J.M. Farley Nuclear Plant Unit 1