ML14133A639

Summary of Telephone Conference Call Held on May 12, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 26, Pertaining to the Byron Station and Br

ML14133A639
Person / Time
Site:	Byron, Braidwood
Issue date:	05/23/2014
From:	Robinson L License Renewal Projects Branch 1
To:	Exelon Generation Co
Robinson L, 415-4115
References
TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882
Download: ML14133A639 (6)

Text

May 23, 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 MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)

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 May 12, 2014, to discuss and clarify the staffs draft request for additional information (DRAI),

Set 26, 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 staffs DRAIs. provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

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

ML14133A639 *concurrence via email OFFICE LA:DLR* PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 5/16/14 5/19/14 5/23/14 5/23/14

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)

DISTRIBUTION EMAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII

TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 12, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)

Seung Min NRC Bart Fu NRC Chris Wilson Exelon Generating Company, LLC (Exelon)

Al Fulvio Exelon Albert Piha Exelon Phil ODonnell Exelon Gary Becknell Exelon Ralph Wolen Exelon Don Brindle Exelon ENCLOSURE 1

DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION May 12, 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 May 12, 2014, to discuss and clarify the following draft request for additional information (DRAI),

Set 26, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).

DRAI 3.1.1.80-1a Applicability:

Byron and Braidwood

Background:

By letter dated March 28, 2014, the applicant responded to RAI 3.1.1.80-1, which addressed LRA item 3.1.1-80. This LRA item states that the Water Chemistry program and One-Time Inspection program are used to manage cracking due to stress corrosion cracking (SCC) for stainless steel or steel with stainless steel pressurizer relief tanks (none-ASME-Section-XI tank shells, heads, flanges and nozzles) exposed to treated borated water > 60°C (>140°F). LRA item 3.1.1-80 corresponds to NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR), Table 3.1-1, item 80, which contains Generic Aging Lessons Learned (GALL) Report item IV.C2.RP-383.

Issue:

During its review of the applicants response to RAI 3.1.1.80-1 and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific AMR line item for GALL Report item IV.C2.RP-383 to manage cracking due to SCC of pressurizer relief tanks in accordance with LRA item 3.1.1-80. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer relief tanks.

Request:

Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel or steel with stainless steel pressurizer relief tanks using LRA item 3.1.1-80. Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-80 to manage cracking due to SCC for these components.

Discussion: The applicant requested clarity on the staffs concern. The applicant informed the staff that the explanation for not including the pressurizer relief tanks was listed in the updated final safety analysis report (UFSAR). After further review of the UFSAR, the staff agreed that this information was docketed and made the determination to withdraw this question. This question will not be sent as part of the formal request.

ENCLOSURE 2

DRAI 3.1.1.81-1a Applicability:

Byron and Braidwood

Background:

By letter dated March 28, 2014, the applicant responded to RAI 3.1.1.81-1, which addressed LRA item 3.1.1-81. This LRA item states that the Water Chemistry program and One-Time Inspection program are used to manage cracking due to SCC for stainless steel pressurizer spray heads exposed to reactor coolant. LRA item 3.1.1-81 corresponds to SRP-LR Table 3.1-1, item 81, which contains GALL Report item IV.C2.RP-41.

Issue:

During its review of the applicants response and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific aging management review (AMR) line item for GALL Report item IV.C2.RP-41, which manages cracking due to SCC of stainless steel pressurizer spray heads in accordance with LRA item 3.1.1-81.

Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer spray heads.

Request:

Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel pressurizer spray heads using LRA item 3.1.1-81.

Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-81 to manage cracking due to SCC for these components.

Discussion: The applicant requested clarity on the staffs concern. No edits were proposed.

This question will be sent as part of the formal request titled: RAI 3.1.1.81-1a.