ML14296A675
| ML14296A675 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/30/2014 |
| From: | Chris Miller Division of License Renewal |
| To: | Gallagher M Exelon Generation Co |
| Robinson L, 301-415-4115 | |
| Shared Package | |
| ML14297A125 | List: |
| References | |
| Download: ML14296A675 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 30, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
SAFETY EVALUATION REPORT WITH OPEN ITEMS RELATED TO THE LICENSE RENEWAL OF BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2
Dear Mr. Gallagher:
By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application to renew operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively. The license renewal application (LRA) was submitted pursuant to Title 10 of the Code of Federal Regulations Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. The staff determined that the LRA was complete and acceptable for docketing on July 16, 2013.
The staff reviewed the Byron Station and Braidwood Station (BBS) LRA and developed the enclosed Safety Evaluation Report with Open Items Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (ADAMS Accession No. ML14296A176) hereinafter referred to as the Safety Evaluation Report (SER). This SER reflects the status of the staffs review of the LRA, requests for additional information (RAIs), the applicants responses to the staffs RAIs, and other questions related to the LRA through October 7, 2014, unless otherwise noted. Issuance of the enclosed SER is an important milestone for both the applicant and the staff.
The staff has identified two open items in its review that must be resolved before it can make a final safety determination on the application. The open items are summarized in SER Section 1.5, along with an explanation of the information required to satisfactorily resolve the issues.
The first open item is referred to as 3.0.3.1.3-1 Nozzle Wear Acceptance Criteria. The applicants control rod drive mechanism (CRDM) penetration nozzles have wear due to interactions with thermal sleeve centering tabs. The applicant did not propose any examinations during the period of extended operation for the areas with wear. The staff requested additional information to confirm that the CRDM penetration nozzle wear will be adequately managed for aging during the period of extended operation. The second open item is referred to as 4.3-1 Environmentally Assisted Fatigue (EAF) in Class 1 Components. The applicant stated that it performed a systematic review to determine the leading locations to be monitored by the Fatigue Monitoring Program for EAF. The systematic review involved grouping Class 1 components into transient sections. However, in justifying its review for transient sections that contained locations of different materials, the applicant did not demonstrate that its methodology for selecting EAF leading locations was bounding. The staff requested that the applicant provide information to demonstrate that specific components would not need to be monitored for EAF in the period of extended operation.
M. Gallagher In accordance with the schedule for completing the review of the BBS LRA, the applicant is requested to review the enclosed SER, verify its accuracy, and provide comments to the staff within 45 days of the date of this letter. The staff plans to review the current content and format of the SER for further improvement, while considering the applicants comments. Upcoming milestones for this project include an Advisory Committee on Reactor Safeguards Subcommittee meeting on December 3, 2014, and a final SER, which is currently scheduled to be issued on or about April 7, 2015.
If you have any questions regarding this matter, please contact the license renewal project manager, Mrs. Lindsay Robinson, at 301-415-4115 or by e-mail at Lindsay.Robinson@nrc.gov.
Sincerely,
/RA/
Christopher G. Miller, Director Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457
Enclosure:
As stated cc w/encl: Listserv
ML14297A125 (Package), ML14296A675 (Letter),
ML14296A176 (Safety Evaluation Report)
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- YEdmonds LRobinson YDiaz-Sanabria DMorey MMarshall DATE 10/27/14 10/29/14 10/29/14 10/29/14 10/29/14 OFFICE BC:DRA:AFPB BC:DSS:SCVB SLS:DLR OGC (NLO)
NAME
- AKlein
- RDennig AHiser
- CEngland MYoung DATE 8/28/2014 7/21/2014 10/29/14 9/22/2014 10/29/14 OFFICE BC:DSS:SRXB BC:DE:EMCB BC:DE:EEEB BC:DSS:SBPB BC:DE:ESGB NAME
- UShoop
- YLi
- JZimmerman
- GCasto
- GKulesa DATE 9/8/2014 8/29/2014 9/4/2014 8/27/2014 9/10/2014 OFFICE DD:DE D:DSS D:DRA DD:DLR D:DLR NAME
- MJRoss-Lee
- TMcGinty
- JGiitter JMarshall CMiller DATE 9/16/2014 9/23/2014 9/15/2014 10/30/14 10/30/14
Letter to Michael Gallagher from Christopher G. Miller dated October 30, 2014
SUBJECT:
SAFETY EVALUATION REPORT WITH OPEN ITEMS RELATED TO THE LICENSE RENEWAL OF BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
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