ML14051A503
| ML14051A503 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/20/2014 |
| From: | Robinson L License Renewal Projects Branch 1 |
| To: | Gallagher M Exelon Generation Co |
| Robinson L, 415-4115 | |
| References | |
| TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 | |
| Download: ML14051A503 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 20, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BYRON NUCLEAR STATION, UNITS 1 AND 2, AND BRAIDWOOD NUCLEAR STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION- SET 17 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
Dear Mr. Gallagher:
By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4115 or by e-mail at Lindsay.Robinson@nrc.gov.
Sincerely,
/
~
Lindsay R. 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
Enclosure:
Request for Additional Information cc: Listserv
March 20, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BYRON NUCLEAR STATION, UNITS 1 AND 2, AND BRAIDWOOD NUCLEAR STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION- SET 17 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
Dear Mr. Gallagher:
By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301 ~415~4115 or e~mail Undsay.Robinson@nrc.gov.
Sincerely, IRA/
Lindsay R. 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
Enclosure:
Request for Additional Information cc w/encl* Listserv DISTRIBUTION: See following pages ADAMS Access1on No* ML14051A503 *concurred via email OFFICE LA:DLW PM: RPB1:DLR PM:RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME IKing LRobinson JDaily YDiazSanabria LRobinson DATE 2/21/14 3/18/14 3/19/14 3/19/14 3/20/14 OFFICIAL RECORD COPY
Letter to M.P. Gallagher from Lindsay R. Robinson dated March 20, 2014
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BYRON NUCLEAR STATION, UNITS 1 AND 2, AND BRAIDWOOD NUCLEAR STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION- SET 17 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
DISTRIBUTION EMAIL:
PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRasb Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson JDaily DMclntyre, OPA JMcGhee, Rill EDuncan, Rill JBenjamin, Rill AGarmoe, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill
BYRON NUCLEAR STATION, UNITS 1 AND 2, AND BRAIDWOOD NUCLEAR STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION- SET 17 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
RAI B.2.1,7-7 Applicability:
Byron Nuclear Station and Braidwood Nuclear Station, all units
Background:
The applicant's pressurized-water reactor (PWR) Vessel Internals aging management program implements the guidance of Materials Reliability Program (MRP)-227-A, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," to manage the aging effects of reactor vessel internals (RVIs) components ApplicanULicensee Action Item No.1 of MRP-227 -A states that each applicanVIicensee shall refer, in particular, to the assumptions regarding plant design and operating history made in the failure modes, effects, and criticality assessment (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 RVI components or plant operating conditions, which result in different component inspection categories. The applicanUiicensee 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 staff's 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)
The staff also noted that by letter dated October 14, 2013, the 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 MRP members to use in developing reactor internals related information for plant-specific inspection 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.
ENCLOSURE
.2.
Request:
- 1. Cold-worked Materials - Do the units have non-weld or bolting austenitic stainless steel 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?