ML14064A391

Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 15

ML14064A391
Person / Time
Site:	Byron, Braidwood
Issue date:	03/11/2014
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: ML14064A391 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 March 11,2014 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 STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION, SET 15 (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 Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively. for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The 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 by Lindsay.Robinson@nrc.gov.

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

March 11, 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 STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION, SET 15 (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 Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The 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 Lindsay.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 A

'on No* ML14064A391 ccess1

• 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 3/6/14 3/6/14 3/6/14 3/6/14 3/11/14 OFFICIAL RECORD COPY

Letter to M.P. Gallagher from Lindsay R. Robinson dated March 11, 2014

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION, SET 15 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)

DISTRIBUTION EMAIL:

PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRasb Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson JDaily DMclnlyre, OPA JMcGhee, Rill EDuncan, Rill JBenjamin, Rill AGarmoe, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill

RAI4.2.3-1 Applicability:

BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION, SET 15 (TAC NOS. MF1879, MF1880, MF1881, MF1882)

Braidwood Station (Braidwood), Unit 2

Background:

License renewal application (LRA) Table 4.2.3-4 provides the numbers used by the applicant to calculate the reference temperature pressurized thermal shock (RT PTs) values for the Braidwood, Unit 2, reactor pressure vessel materials in accordance with Equation 4 in 10 CFR 50.61. In that equation, one of the terms used to calculate RT PTs is the reference temperature for the material in the pre-service or unirradiated condition (RT NDT(U))*

Issue:

For the "Nozzle Shell Forging-to-Intermediate Shell Forging Circ. Weld Seam (Heat# H4498)"

material, LRA Table 4.2.3-4 identifies RT NDT(U) to be -25°F. However, the Updated Final Safety Analysis Report (UFSAR) Table 5.3-10 identifies RT NDT(UJ for the same material (identified as the "Upper Circumferential Weld") to be -30°F.

Request:

For this material, explain the discrepancy between the RT NDT(U} value in the LRA and the RT NDT{Ul value in the UFSAR. Identify the correct value and substantiate it with supporting documentation from the pre-service RT NDT(UJ measurements. If necessary, revise LRA Table 4.2 3-4 accordingly.

RAI B.1.4-1 Applicability:

Byron Station (Byron) and Braidwood

Background:

LRA Section 8.1.4 describes the applicant's process for reviewing future operating experience for the aging management programs (AMPs). The LRA states that operating experience from plant-specific and industry sources will be captured and systematically reviewed on an ongoing basis in accordance with the Quality Assurance program and the Operating Experience program. In addition, the LRA describes several enhancements to the operating experience review process that the applicant will make in order to ensure the effective use of internal and external operating experience related to aging management.

ENCLOSURE LRA Section 8.1.4 states that the Operating Experience program will be enhanced to require station personnel to periodically assess the performance of the AMPs, including insights obtained through operating experience. However, based on the description of this particular enhancement, it is unclear to the NRC staff under what circumstances the applicant will assess the performance of the AMPs. Specifically, it is unclear if the applicant will conduct these assessments regardless of whether the acceptance criteria of the AMPs have been met or not met.

LRA Section 8.1.4 further states that the Operating Experience program will be enhanced to provide training to those personnel responsible for screening, evaluating, and communicating operating experience items related to aging management and age-related degradation.

However, the LRA does not demonstrate that this training will specifically include topics on age-related degradation and aging management.

Request:

1. Describe the circumstances under which the performance of the AMPs will be evaluated and describe how adverse performance results will be identified and processed. Provide justification if these evaluations will only be conducted when the AMP acceptance criteria are not met.

2. Demonstrate that the content of the training activities will include topics on age-related degradation and aging management. Provide justification if the content of the training will not specifically include aging topics.

3. Based on these responses, revise the summary descriptions in LRA Sections A.1.6 and 8.1.4 accordingly.

RAI 8.1.4-2 Applicability:

Byron and Braidwood

Background:

LRA Section A.1.6 provides the UFSAR supplement description of the Operating Experience program and identifies enhancements that will be implemented to ensure that plant-specific and industry operating experience related to aging management will be used effectively.

Issue:

LRA Section 8.1.4 states that the ongoing evaluation of operating experience related to aging management will consider: (a) systems, structures, and components, (b) materials, (c) environments, (d) aging effects, (e) aging mechanisms, (f) AMPs, and (g) activities, criteria, and evaluations integral to the elements of the AMPs. However, LRA Section A.1.6 does not reflect that the evaluation will consider this information.

Request:

Revise LRA Section A.1.6 to reflect the specific information that is considered in the ongoing evaluation of operating experience related to aging management, as stated in LRA Section 8.1.4. Otherwise, provide a justification for not including this information in the UFSAR supplement.