ML16271A449

Transmittal of Summary Technical Reports for Reactor Vessel Specimen Capsule Tests Pursuant to 10 CFR 50, Appendix H and License Renewal Commitment 19

ML16271A449
Person / Time
Site:	Braidwood
Issue date:	09/22/2016
From:	Marchionda-Palmer M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW160072
Download: ML16271A449 (3)

Text

7 Exelon Generation Company, LLC t:!' **' Exelon Generation ., Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 www.exeloncorp.com September 22, 2016 10 CFR Part 50, Appendix H BW160072 10 CFR Part 54 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Transmittal of Summary Technical Reports for Reactor Vessel Specimen Capsule Tests for Braidwood Station, Units 1 and 2, pursuant to 10 CFR 50, Appendix H and related to Braidwood Station, Units 1 and 2, License Renewal Commitment 19

References:

1. Letter from M.P. Gallagher (Exelon Generation Company, LLC) to U.S. NRC, "Response to NRG Request for Additional Information, Set 37, dated July 7, 2014, related to Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application," dated July 28, 2014

2. Letter from C.G. Miller {U.S. NRC) to M.P. Gallagher {Exelon Generation Company, LLC), "Safety Evaluation Report Related to the License Renewal of Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1and2 (TAC Nos. MF1879, MF1880, MF1881, MF1882)," dated July6, 2015 In Section 3.0.3.2.14, "Reactor Vessel Surveillance," of the Reference 2 enclosure, the NRC noted that Appendix H to 10 CFR Part 50 states, "Each capsule withdrawal and the test results must be the subject of a summary technical report to be submitted... within 1 year of the date of capsule withdrawal, unless an extension is granted by the Director, Office of Nuclear Regulatory Regulation." The NRG further stated that upon receiving a renewed operating license, the surveillance capsules identified by Exelon Generation Company, LLC (EGG) as standby capsules would no longer be considered standby capsules; instead, they would be considered part of the program to meet the recommendations of the GALL Report and the requirements of 10 CFR Part 50, Appendix H. The staff found that since the standby capsules had already been removed from the reactor vessels, they should be tested and summary reports should be submitted within one year of receiving the renewed license, unless the station submits a r~quest for extension for approval by the Director, Office of Nuclear Reactor Regulation, within this period. Since Braidwood Station, Units 1 and 2 renewed licenses were issued on January 27, 2016, Braidwood Station is*to submit test results for the tested capsules by January 27, 2017.

September 22, 2016 U.S. Nuclear Regulatory Commission Page2 In Reference 1, EGG updated License Renewal Application Appendix A, Table A.5, "License Renewal Commitment List," adding Enhancement 2 to Commitment 19 in response to NRC Request for Additional Information (RAI) B.2.1.19-1 b. Enhancement 2 reads as follows, with Byron capsules not included for the purpose of the Braidwood response:

"One (1) specimen capsule per reactor vessel, as designated below, irradiated to a neutron fluence of one (1) to two (2) times the projected peak neutron fluence at the end of the period of extended operation will be withdrawn from the spent fuel pool, tested,

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and the summary technical report subm(tted to the NRG within one (1) year of receipt of the renewed license. Alternatively, if a request for extension of the testing schedule is submitted in accordance with 10 CFR 50, Appendix H and granted by the Director, Office of Nuclear Reactor Regulation, specimen testing will be performed in accordance with that approved extension."

Reactor Vessel Capsule ID Capsule Fluence (Station, Unit) (nlcrrr)(E>1.0 MeV)

Braidwood Station, Unit 1 v 3.71E+19 Braidwood Station, Unit 2 v 3.73E+19 To satisfy 10 CFR 50, Appendix H requirements, Attachments 1 and 2 to this letter provide the testing results for Braidwood Station, Unit 1, Capsule V and Braidwood Station, Unit 2, Capsule V identified in the table above. The attachment evaluations led to the following conclusions:

• Unit 1 Capsule V received a fluence of 3.71 x 1019 n/cm 2 (E> 1.0 MeV) after irradiation to 17.69 EFPY, and the peak clad/base metal interface vessel fluence after 57 EFPY (end-of-license extension) of plant operation is projected to be 3.22 x 1019 n/cm 2 (E> 1.0 MeV).

• Unit 2 Capsule V received a fluence of 3.73 x 1019 n/cm 2 (E> 1.0 MeV) after irradiation to 18.41 EFPY, and the peak clad/base metal interface vessel fluence after 57 EFPY (end-of-license extension) of plant operation is projected to be 2.95 x 1019 n/cm 2 (E> 1.0 MeV).

• For the Unit 1 and Unit 2 capsules, the measured percent decreases in upper-shelf energy for the surveillance forging and weld materials are less than the Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2 predictions.

• For the Unit 1 and Unit 2 capsules, with consideration of surveillance data, all beltline and extended beltline materials exhibit adequate upper-shelf energy levels for continued safe plant operation and are predicted to maintain an upper-shelf energy greater than 50 ft-lb through end-of-license extension (57 EFPY) as required by 1o CFR 50, Appendix G.

This submittal also satisfies the requirement in Enhancement 2 of license renewal Commitment 19 to submit a capsule test summary technical report within one year of receipt of the renewed license for Braidwood Station, Units 1 and 2.

September 22, 2016 U.S. Nuclear Regulatory Commission*

Page3 There are no new regulatory commitments in this letter.

Should you have any questions concerning this submittal, please contact Mr. Steven Reynolds, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully,

/7]MAU /!Ji/fJvc)_-YY) ~

Marri Marchionda-Palmer Site Vice President Braidwood Station Attachments: 1. WCAP-18092-N P, Revision 1, "Analysis of Capsule V from the Exelon Generation Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program," dated May 2016

2. WCAP-18107-NP, Revision 0, "Analysis of Capsule Vfrom the Exelon I Generation Braidwood Unit 2 Reactor Vessel Radiation Surveillance ,~

Program," dated May 2016 cc: Regional Administrator - NRC Region Ill NRC Project Manager - Braidwood and Byron Stations NRC Senior Resident Inspector - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety