ML14058B180

Summary of Telephone Conference Call on February 18, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Regarding Byron & Braidwood Stations, License Renewal

ML14058B180
Person / Time
Site:	Byron, Braidwood
Issue date:	03/11/2014
From:	Robinson L License Renewal Projects Branch 1
To:
Robinson L, 415-4115
References
TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882
Download: ML14058B180 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

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LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 18, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE BYRON NUCLEAR STATION AND BRAIDWOOD NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND MF1882)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC, held a telephone conference call on February 18, 2014, to discuss and clarify the staff's draft request for additional information (ORAl), Set 17, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's ORAls.

Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

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Projects Branch 1

--

Lindsay Robinson, Project Manager Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457

Enclosures:

1. List of Participants 2 List of Draft Request for Additional Information cc w/encls: Listserv

March 11,2014 LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 18, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND MF1882)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC, held a telephone conference call on February 18, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), Set 17, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAis. provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

IRA!

Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457

Enclosures:

1. List of Participants

2. List of Draft Request for Additional Information cc w/encls: Listserv DISTRIBUTION: See next page ADAMS A cc esso 1 n No.: ML14058B180 *concurred via email OFFICE LA:DLR' PM: RPB1 :DLR PM:RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME I King LRobinson JDaily YDiazSanabria LRobinson DATE 2128114 316114 316114 3110114 3111114 OFFICIAL RECORD COPY

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 18, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE BYRON NUCLEAR STATION AND BRAIDWOOD NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)

DISTRIBUTION EMAIL:

PUBLIC RidsNrrD!r Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsOgcMai\Center RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson JOaily DMclntyre, OPA EDuncan, Rill JBenjamin, Rill AGarmoe, Rill JMcGhee, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill

TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS February 18, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)

John Daily NRC Mark Yoo NRC On Vee NRC John Hufnagel Exelon Generating Company, LLC (Exelon)

Albert Piha Exelon Gary Becknell Exelon Don Brindle Exelon RalphWolen Exelon ENCLOSURE 1

DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON NUCLEAR STATION, UNITS 1 AND 2 AND BRAIDWOOD NUCLEAR STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION February 18, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on February 18, 2014, to discuss and clarify the following draft request for additional information (ORAl) concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).

ORAl B.2.1.7-7 Applicability:

Byron Station (Byron) and Braidwood Station (Braidwood), all units

Background:

The applicant's PWR Vessel Internals aging management program implements the guidance of MRP-227-A, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," to manage the aging effects of reactor vessel internals components.

Applicant/Licensee Action Item No.1 of MRP-227 -A states that each applicant/licensee shall refer, in particular, to the assumptions regarding plant design and operating history made in the failure models, effects, and criticality analysis (FMECA) and functionality analyses for reactors of their design (i.e., Westinghouse, CE, or B&W) which support MRP-227 and describe the process used for determining plant-specific differences in the design of their reactor vessel internal (RVI) components or plant operating conditions, which result in different component inspection categories. The applicant/licensee shall submit this evaluation for NRC review and approval as part of its application to implement the approved version of MRP-227. The applicant provided its response to Applicant/Licensee Action Item No.1 in license renewal application (LRA) Appendix C.

Issue:

The staff noted that the applicant's response to Applicant/Licensee Action Item No.1 did not adequately address the three key variables at the applicant's sites that feed into the screening process for aging degradation (stress, neutron fluence, and temperature) and determine how these variations, if any, would ultimately affect the aging management recommendations.

The staffs concern was addressed generically with the industry as documented in the following documents: "Meeting Summary EPRI-Westinghouse January, 22-23, 2013 (ADAMS Accession No. ML13042A048) and "Summary of Telecom with EPRI and Westinghouse Electric Company" on February 25, 2013 (ADAMS Accession No. ML13067A262).

ENCLOSURE 2

The staff also noted that by letter dated October 14, 2013, the Materials Reliability Program (MRP) issued EPRI Letter MRP 2013-025. The staff noted that the purpose of this letter was to provide an MRP-227 -A related guidance document for Materials Reliability Program members to use in developing reactor internals related information for plant-specific programs. Specifically, the enclosure was developed to provide utilities with the basis for a plant to respond to the NRC's Request for Additional Information (RAI) to demonstrate compliance with the basic technical applicability assumptions in MRP-227 -A for originally licensed and uprated conditions.

Request:

1. Cold-worked Materials - Do the units have non-weld or bolting austenitic stainless steel (SS) components with 20 percent cold work or greater; and if so, do the affected components have operating stresses greater than 30 ksi? (The staff notes that if both conditions are true, then additional components may need to be screened in for stress corrosion cracking.)

2. Fuel Design or Fuel Management- Does the plant have atypical fuel design or fuel management that could render the assumptions of MRP-227 -A, regarding core loading/core design, non-representative for that plant?

Discussion: The applicant requested the staff clarify its request The applicant then explained the resources required to acquire the information, which the staff acknowledged. No edits were requested. This question will be sent as a formal RAI titled: "RAI 8.2.1.7-7."