ML15175A062

Summary of Telephone Conference Call Held on May 18, 2015, Between the U.S. Nuclear Regulatory Commission and DTE Electric Company, Concerning RAIs Pertaining to the Fermi 2 LRA

ML15175A062
Person / Time
Site:	Fermi
Issue date:	07/06/2015
From:	Melendez-Colon D License Renewal Projects Branch 1
To:
Melendez-Colon D, NRR/DLR, 415-3301
References
DLR-15-0313, TAC MF4222
Download: ML15175A062 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 6, 2015 LICENSEE:

DTE Electric Company FACILITY:

Fermi 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 18, 2015, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND DTE ELECTRIC COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE FERMI 2 LICENSE RENEWAL APPLICATION (TAC NO. MF4222)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of DTE Electric Company (DTE or the applicant) held a telephone conference call on May 18, 2015, to discuss and clarify the staffs draft request for additional information (DRAI) 4.1-4a concerning the Fermi 2 license renewal application. The telephone conference call was useful in clarifying the intent of the staffs DRAI.

provides a listing of the participants and Enclosure 2 contains a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Daneira Meléndez-Colón, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosures:

1. List of Participants

2. Summary of Telephone Conference Call cc: Listserv

ML15175A062

• Concurred via e-mail OFFICE LA:RPB1:DLR*

PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds DMeléndez-Colón YDíaz-Sanabria DMeléndez-Colón DATE 6/30/15 7/2/15 7/6/15 7/6/15

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 18, 2015, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND DTE ELECTRIC COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE FERMI 2 LICENSE RENEWAL APPLICATION (TAC NO. MF4222)

DISTRIBUTION:

E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRsrg Resource RidsNrrPMFermi2 Resource D. Melendez-Colon E. Keegan B. Wittick B. Harris, OGC D. Roth, OGC M. Kunowski, RIII B. Kemker, RIII V. Mitlyng, RIII P. Chandrathil, RIII

ENCLOSURE 1 TELEPHONE CONFERENCE CALL FERMI 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 18, 2015 PARTICIPANTS AFFILIATIONS Daneira Meléndez-Colón U. S. Nuclear Regulatory Commission (NRC)

Matthew Hardgrove NRC Mark Yoo NRC James Medoff NRC Yoira Díaz-Sanabria NRC Christopher Jackson NRC Allen Hiser NRC Lynne Goodman DTE Electric Company (DTE)

Kevin Lynn DTE Erica Mullen DTE James Thorson DTE Ethan Hauser DTE

ENCLOSURE 2

SUMMARY

OF TELEPHONE CONFERENCE CALL FERMI 2 LICENSE RENEWAL APPLICATION MAY 18, 2015 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of DTE Electric Company (DTE or the applicant) held a telephone conference call on May 18, 2015, to discuss and clarify the following draft request for additional information (DRAI) concerning the Fermi 2 license renewal application (LRA).

DRAI 4.1-4a

Background:

The response to Request for Additional Information (RAI) 4.1-4, dated February 5, 2015, states that the standby liquid control (SLC)/core P lines internal to the reactor pressure vessel (RPV) do not perform a license renewal intended function. A proprietary response to RAI 4.1-4, Part 2, which requested a clarification on whether the current licensing basis included any analyses for the internal portions of the SLC system that would need to be identified as time-limited aging analyses (TLAAs), was also provided.

Updated Final Safety Analysis Report (UFSAR) Section 4.5.1.2.11 indicates that the internal portions of the SLC/core P piping consists of two concentric pipes that enter into the RPV lower plenum area and that the inner piping serves the following objectives: (a) facilitates good mixing and dispersion of the sodium pentaborate in the SLC system, and (b) reduces thermal shock to the RPV nozzle should the SLC system be actuated. UFSAR Section 4.5.2.4.1 states that the SLC system supports a number of design bases, including the design basis that the neutron absorber shall be dispersed with the reactor core in sufficient quantity to provide a reasonable margin for leakage or imperfect mixing.

Issue:

Based on information provided in UFSAR Sections 4.5.1.2.11 and 4.5.2.4.1, the staff has concluded that internal portions of the SLC line (i.e., the portions of the line inside of the reactor pressure vessel) need to be included within the scope of license renewal in accordance with either: (a) Title 10 of the Code of Federal Regulations (10 CFR) 54.4(a)(2), where its failure could potentially impact the ability of the SLC/core P nozzle to achieve its reactor coolant pressure boundary function, or (b) 10 CFR 54.4(a)(3) for mitigating the consequences of anticipated transients without scram (ATWS) events.

Request:

a. Justify why the structural integrity of the internal portions of the SLC/core P line has not been identified as an intended function for the LRA and why the internal portions of the SLC/core P line have not been identified as being within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). In addition, justify why the internal portions of the SLC/core P line would not need to be within the scope of license renewal in accordance with the requirement in 10 CFR 54.4(a)(3).

b. If it is determined that the internal portions of the SLC/core P line do serve license renewal intended functions, justify why the application would not need to be amended to include the internal portions of the SLC line as a component that needs to be within the scope of license renewal in accordance with the requirements in 10 CFR 54.4(a)(2) or 10 CFR 54.4(a)(3) for regulated ATWS events.

c. State the applicable aging effects requiring management that apply to the components and state (with justification) how these aging effects will be managed during the period of extended operation. Otherwise, justify why the applicable aging effects do not need to be age-managed if condition monitoring activities (i.e., inspections) will not be performed on the internal portions of the SLC during the period of extended operation.

Discussion:

The staff provided clarification related to its concern in draft RAI 4.1-4a. Specifically, the staff provided clarification regarding its conclusion that internal portions of the SLC line (i.e., the portions of the line inside the reactor pressure vessel) need to be included within the scope of license renewal.

The applicant stated that its scoping determination is performed on a system basis and that the screening portion is performed on a component basis.

The applicant and the staff discussed the mixing and reduction in thermal shock objectives of the SLC inner piping.

The staff provided additional clarification related to Request a.

The applicant understands the staffs concerns and will provide a response to the RAI.

This request will be sent as a formal RAI.